WorldWideScience

Sample records for refueling

  1. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

    1981-01-01

    An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

  2. Reactor refueling machine simulator

    International Nuclear Information System (INIS)

    Rohosky, T.L.; Swidwa, K.J.

    1987-01-01

    This patent describes in combination: a nuclear reactor; a refueling machine having a bridge, trolley and hoist each driven by a separate motor having feedback means for generating a feedback signal indicative of movement thereof. The motors are operable to position the refueling machine over the nuclear reactor for refueling the same. The refueling machine also has a removable control console including means for selectively generating separate motor signals for operating the bridge, trolley and hoist motors and for processing the feedback signals to generate an indication of the positions thereof, separate output leads connecting each of the motor signals to the respective refueling machine motor, and separate input leads for connecting each of the feedback means to the console; and a portable simulator unit comprising: a single simulator motor; a single simulator feedback signal generator connected to the simulator motor for generating a simulator feedback signal in response to operation of the simulator motor; means for selectively connecting the output leads of the console to the simulator unit in place of the refueling machine motors, and for connecting the console input leads to the simulator unit in place of the refueling machine motor feedback means; and means for driving the single simulator motor in response to any of the bridge, trolley or hoist motor signals generated by the console and means for applying the simulator feedback signal to the console input lead associated with the motor signal being generated by the control console

  3. A TRIGA refueling exercise

    Energy Technology Data Exchange (ETDEWEB)

    McEwen, Michael J [Kansas State University (United States)

    1974-07-01

    In June 1973 the U.S. Atomic Energy Commission offered to assist the Department of Nuclear Engineering staff in refueling the KSU TRIGA Mkll - Nuclear Reactor. The replacement fuel was made available free of charge and a contract was negotiated between the Department of Nuclear Engineering and the A.E.C. to provide for costs incurred during the refueling operation. In addition, the A.E.C. aided in the fuel transfers by providing the names of contacts at the different laboratories and agencies concerned with fuel transfers. Data and numbers relevant to the entire reloading will be available in the short summary. (author)

  4. Refueling of nuclear reactor

    International Nuclear Information System (INIS)

    Kaufmann, J.W.; Swidwa, K.J.; Hornak, L.P.

    1989-01-01

    This patent describes an apparatus for refueling a nuclear reactor, the reactor being disposed for refueling under water in a pit in a containment, the apparatus including a bridge to be mounted moveably over the pit on the containment, first means connected to the bridge, for moving the bridge forward and backward on the containment over the pit along a first path, a first pulse generator, connected to the moving means, responsive to the movement of the bridge, for producing pulses, means, connected to the generator,for counting the pulses, the count of the pulses being dependent on the distance of the movement of the bridge

  5. Development of refueling support system

    International Nuclear Information System (INIS)

    Nishimura, Hiroshi; Hayashi, Shoichi; Sano, Kazuya; Hochin, Koji; Iguchi, Yukihiro

    1992-01-01

    The refueling of Fugen Nuclear Power Station requires correct management of fuels, etc. And empirical knowledge is necessary for efficient planning and refueling. Fugen developed refueling support system and put it into practical operation. The system features a network of refueling equipment and AI rules aquired from operators knowledge. The system helps make an optimized plan, displays step-by-step guidance and prints out lists of fuel locations and movements. The system reduced the labor of the operators, optimized the management and improved the reliability of the refueling. (author)

  6. Robotic refueling machine

    International Nuclear Information System (INIS)

    Challberg, R.C.; Jones, C.R.

    1996-01-01

    One of the longest critical path operations performed during the outage is removing and replacing the fuel. A design is currently under development for a refueling machine which would allow faster, fully automated operation and would also allow the handling of two fuel assemblies at the same time. This design is different from current designs, (a) because of its lighter weight, making increased acceleration and speed possible, (b) because of its control system which makes locating the fuel assembly more dependable and faster, and (c) because of its dual handling system allowing simultaneous fuel movements. The new design uses two robotic arms to span a designated area of the vessel and the fuel storage area. Attached to the end of each robotic arm is a lightweight telescoping mast with a pendant attached to the end of each mast. The pendant acts as the base unit, allowing attachment of any number of end effectors depending on the servicing or inspection operation. Housed within the pendant are two television cameras used for the positioning control system. The control system is adapted from the robotics field using the technology known as machine vision, which provides both object and character recognition techniques to enable relative position control rather than absolute position control as in past designs. The pendant also contains thrusters that are used for fast, short distance, precise positioning. The new refueling machine system design is capable of a complete off load and reload of an 872 element core in about 5.3 days compared to 13 days for a conventional system

  7. Diablo Canyon refueling outage program

    International Nuclear Information System (INIS)

    McLane, W.B.; Irving, T.L.

    1991-01-01

    Management of outages has become one of the most talked about subjects in the nuclear power industry in the past several years. Many utilities do not perform refueling outages very well or in the past have had some outages that they would not like to repeat and in some cases do not even like to think about. With the growing cost of energy and the demands placed on utilities to improve capacity factors, it is very easy for management to focus on shortening refueling outage durations as a prime objective in improving overall corporate performance. So it is with Pacific Gas and Electric Company and the Diablo Canyon power plant. A review of their refueling outage performance reflects a utility that is responding to the nuclear industry's call for improved outage performance

  8. Support services to refuelling exploitation

    International Nuclear Information System (INIS)

    Castineira, M; Cortes, M.; Rayo, A.

    2010-01-01

    The refuelling period in nuclear power stations is very important due to the need to optimise its duration, large volumes of work and resources that have to be planned and coordinated and their impact on the subsequent operating cycle. Empresarios Agrupados has a permanent organisation, with specialised resources and extensive availability of human resources. (Author)

  9. Hydrant refueling system as an optimisation of aircraft refuelling

    Directory of Open Access Journals (Sweden)

    Martin HROMÁDKA

    2015-09-01

    Full Text Available At large international airports, aircraft can be refuelled either by fuel trucks or using dedicated underground pipeline systems. The latter, hydrant refuelling, is considered to be an optimal fuelling method as it increases safety, shortens the aircraft turnaround time and cuts the overall costs. However, at smaller airports, implementation of this system can lead to high investment costs. Thus, the paper discusses the airport size from which this system may be efficient to implement. Various definitions of term “airport size” are assessed. Based on data collection, the hydrant system model is created within the paper. As a result, methodology for assessing the suitability of hydrant system implementation is set. This methodology can be used at every airport using three simple inputs.

  10. Pellet refueling program at Risoe

    International Nuclear Information System (INIS)

    Andersen, V.; Chang, C.T.; Joergensen, L.W.; Nielsen, P.; Sillesen, A.H.

    1978-01-01

    The pellet refueling work at Riso has up to now been concentrated at studying the ablation rate of hydrogen pellets in hydrogen and deuterium plasmas in the Puffatron device. The main results of these studies are well known and we shall only give a brief summary including some more recent results relating to the ablation process. The work on the Puffatron device has been completed and we are presently preparing to start ablation studies in a small Tokamak, Dante. This tokamak has only been constructed this summer and ablation studies are expected to begin in the beginning of 1978. We shall give the expected parameters of the tokamak plasma and indicate some of the planned work. In this presentation we shall also report on the theoretical work on refueling taking place at Riso. We have particularly been interested in the effect of α-particles which could significantly alter the conclusions made from present experiments

  11. Nuclear reactor machine refuelling system

    International Nuclear Information System (INIS)

    Cashen, W.S.; Erwin, D.

    1977-01-01

    Part of an on-line fuelling machine for a CANDU pressure-tube reactor is described. The present invention provides a refuelling machine wherein the fuelling components, including the fuel carrier and the closure adapter, are positively positioned and retained within the machine magazine or positively secured to the machine charge tube head, and cannot be accidentally disengaged as in former practice. The positive positioning devices include an arcuate keeper plate. Simplified hooked fingers are used. (NDH)

  12. Automated refueling inventory control system at FFTF

    International Nuclear Information System (INIS)

    Ordonez, C.R.

    1983-10-01

    The Refueling Inventory Control System (RICS) at the Fast Flux Test Facility (FFTF) keeps track of all assemblies that reside in the various refueling facilities. The automated RICS allows the user to obtain information regarding any assembly under its control by displaying the data on a screen. It also provides a simulation mode which allows assembly moves on a duplicated data base. This simulation is used to verify the refueling documentation before it is issued

  13. Improving refueling outages through partnership

    International Nuclear Information System (INIS)

    Mercado, Angelo L.

    2004-01-01

    This paper describes an approach to reduce nuclear plant outage duration and cost through partnership. Partnership is defined as a long-term commitment between the utility and the vendor with the objective of achieving shared business goals by maximizing the effectiveness of each party's resources. The elements of an effective partnership are described. Specific examples are given as to how partnership has worked in the effective performance of refueling outages. To gain the full benefits of a partnership, both parties must agree to share information, define the scope early, communicate goals and expectations, and identify boundaries for technical ownership. (author)

  14. Compact toroid refueling of reactors

    International Nuclear Information System (INIS)

    Gouge, M.J.; Hogan, J.T.; Milora, S.L.; Thomas, C.E.

    1988-04-01

    The feasibility of refueling fusion reactors and devices such as the International Thermonuclear Engineering Reactor (ITER) with high-velocity compact toroids is investigated. For reactors with reasonable limits on recirculating power, it is concluded that the concept is not economically feasible. For typical ITER designs, the compact toroid fueling requires about 15 MW of electrical power, with about 5 MW of thermal power deposited in the plasma. At these power levels, ideal ignition (Q = ∞) is not possible, even for short-pulse burns. The pulsed power requirements for this technology are substantial. 6 ref., 1 figs

  15. Method for refuelling a nuclear reactor core

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This invention relates to an improved method for refuelling a nuclear reactor core inside a reactor vessel. The technique allows a substantial reduction in the refuelling time as compared with previously known methods and permits fewer out of core operations and smaller temporary storage space. (U.K.)

  16. Refueling machine for a nuclear reactor

    International Nuclear Information System (INIS)

    Kowalski, E.F.; Hornak, L.P.; Swidwa, K.J.

    1981-01-01

    An improved refuelling machine for inserting and removing fuel assemblies from a nuclear reactor is described which has been designed to increase the reliability of such machines. The system incorporates features which enable the refuelling operation to be performed more efficiently and economically. (U.K.)

  17. Enhanced methods for operating refueling station tube-trailers to reduce refueling cost

    Science.gov (United States)

    Elgowainy, Amgad; Reddi, Krishna

    2017-08-22

    A method and apparatus are provided for operating a refueling station including source tube-trailers and at least one compressor to reduce refueling cost. The refueling station includes a gaseous fuel supply source including a plurality of tanks on a tube trailer coupled to a first control unit, and high pressure buffer storage having predefined capacity coupled to a second control unit and the first tanks by a pressure control valve and the first control unit, and at least one compressor. The refueling station is operated at different modes depending on a state of the refueling station at the beginning of each operational mode. The refueling system is assessed at the end of each operational mode to identify the state of the system and select a next mode of operation. The operational modes include consolidating hydrogen, or any gaseous fuel, within the tubes mounted on the trailer.

  18. Refueling and control of RFP burns

    International Nuclear Information System (INIS)

    Nebel, R.; Miley, G.H.

    1978-01-01

    An earlier study of the stability of a fusion burn in a Reversed Field Pinch (RFP) has been extended to include cold particle refueling. This refueling, coupled with anomalous transport, makes possible quasi-steady state operation which both flattens the wall-loading temporal dependence and significantly increases energy gain factors. This paper discusses results of these burn simulations along with parametric studies aimed at determining associated reactor scaling problems

  19. Hydrogen Production for Refuelling Applications

    Energy Technology Data Exchange (ETDEWEB)

    Hulteberg, Christian; Aagesen, Diane (Intelligent Energy, Long Beach, CA (United States))

    2009-08-15

    The aim of this work is to support the development of a high-profile demonstration of hydrogen generation technologies in a Swedish context. The overall objective of the demonstration is to deploy a reforming based hydrogen refilling station along the Swedish west coast; intermediate to the Malmoe refuelling station and planned stations in Goeteborg. In this way, the Norwegian hydrogen highway will be extended through the south of Sweden and down into Denmark. The aim of the project's first phase, where this constitutes the final report, was to demonstrate the ability to operate the IE reforming system on the E.On/SGC site-specific fuel. During the project, a preliminary system design has been developed, based on IE's proprietary reformer. The system has been operated at pressure, to ensure a stable operation of the downstream PSA; which has been operated without problems and with the expected hydrogen purity and recovery. The safe operation of the proposed and tested system was first evaluated in a preliminary risk assessment, as well as a full HazOp analysis. A thorough economic modelling has been performed on the viability of owning and operating this kind of hydrogen generation equipment. The evaluation has been performed from an on-site operation of such a unit in a refuelling context. The general conclusion from this modelling is that there are several parameters that influence the potential of an investment in a Hestia hydrogen generator. The sales price of the hydrogen is one of the major drivers of profitability. Another important factor is the throughput of the unit, more important than efficiency and utilization. Varying all of the parameters simultaneously introduce larger variations in the NPV, but 60% of the simulations are in the USD 90 000 to USD 180 000 interval. The chosen intervals for the parameters were: Hydrogen Sales Price (USD 5 - USD 7 per kg); Investment Cost (USD 70 000 - USD 130 000 per unit); Throughput (20 - 30 kg

  20. RFSP simulations of Darlington FINCH refuelling transient

    International Nuclear Information System (INIS)

    Carruthers, E.V.; Chow, H.C.

    1997-01-01

    Immediately after refuelling of a channel, the fresh bundles are free of fission products. Xenon-135, the most notable of the saturating fission products, builds up to an equilibrium level in about 30 h. The channel power of the refuelled channel would therefore initially peak and then drop to a steady-state level. The RFSP code can track saturating-fission-product transients and power transients. The Fully INstrumented CHannels (FINCHs) in Darlington NGS provides channel power data on the refuelling power transients. In this paper, such data has been used to identify the physical evidence of the fission-product transient effect on channel power, and to validate RFSP fission-product-driver calculation results. (author)

  1. Refueling machine with relative positioning capability

    International Nuclear Information System (INIS)

    Challberg, R.C.; Jones, C.R.

    1998-01-01

    A refueling machine is disclosed having relative positioning capability for refueling a nuclear reactor. The refueling machine includes a pair of articulated arms mounted on a refueling bridge. Each arm supports a respective telescoping mast. Each telescoping mast is designed to flex laterally in response to application of a lateral thrust on the end of the mast. A pendant mounted on the end of the mast carries an air-actuated grapple, television cameras, ultrasonic transducers and waterjet thrusters. The ultrasonic transducers are used to detect the gross position of the grapple relative to the bail of a nuclear fuel assembly in the fuel core. The television cameras acquire an image of the bail which is compared to a pre-stored image in computer memory. The pendant can be rotated until the television image and the pre-stored image match within a predetermined tolerance. Similarly, the waterjet thrusters can be used to apply lateral thrust to the end of the flexible mast to place the grapple in a fine position relative to the bail as a function of the discrepancy between the television and pre-stored images. 11 figs

  2. Refueling machine with relative positioning capability

    Science.gov (United States)

    Challberg, R.C.; Jones, C.R.

    1998-12-15

    A refueling machine is disclosed having relative positioning capability for refueling a nuclear reactor. The refueling machine includes a pair of articulated arms mounted on a refueling bridge. Each arm supports a respective telescoping mast. Each telescoping mast is designed to flex laterally in response to application of a lateral thrust on the end of the mast. A pendant mounted on the end of the mast carries an air-actuated grapple, television cameras, ultrasonic transducers and waterjet thrusters. The ultrasonic transducers are used to detect the gross position of the grapple relative to the bail of a nuclear fuel assembly in the fuel core. The television cameras acquire an image of the bail which is compared to a pre-stored image in computer memory. The pendant can be rotated until the television image and the pre-stored image match within a predetermined tolerance. Similarly, the waterjet thrusters can be used to apply lateral thrust to the end of the flexible mast to place the grapple in a fine position relative to the bail as a function of the discrepancy between the television and pre-stored images. 11 figs.

  3. Moved range monitor of a refueling machine

    International Nuclear Information System (INIS)

    Nakajima, Masaaki; Sakanaka, Tadao; Kayano, Hiroyuki.

    1976-01-01

    Purpose: To incorporate light receiving and emitting elements in a face monitor to thereby increase accuracy and reliability to facilitate handling in the refueling of a BWR power plant. Constitution: In the present invention, a refueling machine and a face monitoring light receiving and emitting elements are analogously coupled whereby the face monitoring light receiving and emitting elements may be moved so as to be analogous to a route along which the refueling machine has moved. A shielding plate is positioned in the middle of the light receiving and emitting elements, and the shielding plate is machined so as to be outside of action. The range of action of the refueling machine may be monitored depending on the light receiving state of the light receiving element. Since the present invention utilizes the permeating light as described above, it is possible to detect positions more accurately than the mechanical switch. In addition, the detection section is of the non-contact system and the light receiving element comprises a hot cell, and therefore the service life is extended and the reliability is high. (Nakamura, S.)

  4. On Power Refueling Management of HTR-PM

    International Nuclear Information System (INIS)

    Sun Furui; Luo Yong; Gao Qiang

    2014-01-01

    The refueling management is an important work of nuclear power plant , directly affecting its safety and economy. At present, the ordinary commercial pressurized water reactor (PWR) nuclear power plant has developed more mature in the refueling management, and formed a set of relatively complete system and methods.The High Temperature Gas-cooled Reactor Pebble-modules Demonstration Project(HTR-PM) has significant differences with the ordinary PWR nuclear power plant in the fuel morphology and the refueling mode. It adopts the spherical fuel element and the on-power refueling. Therefore, the HTR-PM refueling management has its own unique characteristics, but currently there is no mature experience to use for reference across the world. This paper gives a brief introduction to the HTR-PM on power refueling management, including the refueling management system construction, the refueling strategy, the fuel element internal transportation,charging and discharging, etc. It aims at finding the befitting HTR-PM refueling management methods in view of its own unique characteristics in order to ensure the orderly development of the refueling management and the refueling safety. (author)

  5. AHTR Refueling Systems and Process Description

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-15

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

  6. AHTR Refueling Systems and Process Description

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

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

  7. Joint deployment of refuelling infrastructure and vehicles

    International Nuclear Information System (INIS)

    Smith, R.

    2010-01-01

    A wide range of fuels will be used in future transportation technologies. This presentation discussed refuelling infrastructure solutions for alternative fuels. A well-placed demonstration infrastructure will help to accelerate market development. Stakeholder collaboration is needed to create high value business paradigms and identify stakeholder benefits. Infrastructure paradigms include the home; businesses; retail public refuelling forecourts; and multi-fuel waste heat recovery sites. Commercial nodes can be developed along major transportation routes. Stakeholder groups include technology providers, supply chain and service providers, commercial end-users, and government. A successful alternative fuel infrastructure model will consider market development priorities, time frames and seed investment opportunities. Applications must be market-driven in order to expand. A case study of the natural gas vehicle (NGV) program in Ontario was also discussed, as well as various hydrogen projects. tabs., figs.

  8. Refueling system for a nuclear reactor

    International Nuclear Information System (INIS)

    Koschkin, J.N.; Ordynskij, G.V.; Schchijan, C.G.; Schapkin, A.F.; Fadeev, A.I.; Laptev, F.V.; Batjukov, V.I.; Korolkov, K.I.; Borodin, I.V.; Tschernomordik, E.N.

    1979-01-01

    With the refueling system fuel elements are transferred from the intermediate distributing chamber within the fast breeder reactor vessel to the storage tanks for new and irradiated fuel elements outside of the reactor vessel and vice versa. It consists of a hermetic chamber, filled with inert gas, within which the refueling machine, having got a vertical swing pipe, is placed. On the swing pipe there is mounted by means of a bracket a hanging support tube for a tube manipulator that can be moved over the openings to the fuel elements. At the end of the tube manipulator there is a gripping device whose drive mechanism is arranged within the support tube. The swing pipe is moved by means of a drive mechanism outside of the chamber. (DG) [de

  9. Aerial Refueling Boom/Receptacle Guide

    Science.gov (United States)

    2017-07-28

    Collision Beacon 22 9.6.2 Tanker Identity Platform Illumination 22 9.6.3 Formation Lights 22 9.6.4 Tanker/Receiver Aircraft...unlatch the receptacle door lock system, mechanical, electrical or hydraulic. Some airplanes will have a master refuel switch which energizes the...some receiver aircraft, pulling the manual door control handle to the detented “DOOR OPEN” position will release the receptacle door lock and

  10. Refueling system for the gas-cooled fast breeder reactor

    International Nuclear Information System (INIS)

    Hawke, B.C.

    1980-05-01

    Criteria specifically related to the handling of Gas-Cooled Fast Breeder Reactor (GCFR) fuel are briefly reviewed, and the most significant requirements with which the refueling system must comply are discussed. Each component of the refueling system is identified, and a functional description of the fuel handling machine is presented. An illustrated operating sequence describing the various functions involved in a typical refueling cycle is presented. The design status of components and subsystems selected for conceptual development is reviewed, and anticipated refueling time frames are given

  11. Optimization of hydrogen vehicle refueling via dynamic simulation

    DEFF Research Database (Denmark)

    Rothuizen, Erasmus Damgaard; Mérida, W.; Rokni, Masoud

    2013-01-01

    loss in the vehicle's storage system is one of the main factors determining the mass flow and peak cooling requirements of the refueling process. The design of the refueling station does not influence the refueling of the vehicle when the requirements of the technical information report J2601 from...... Society of Automotive Engineers are met. However, by using multiple pressure stages in the tanks at the refueling station (instead of a single high-pressure tank), the total energy demand for cooling can be reduced by 12%, and the compressor power consumption can be reduced by 17%. The time between...

  12. Turn of the century refueling: A review of innovations in early gasoline refueling methods and analogies for hydrogen

    International Nuclear Information System (INIS)

    Melaina, Marc W.

    2007-01-01

    During the first decades of the 20th century, a variety of gasoline refueling methods supported early US gasoline vehicles and successfully alleviated consumer concerns over refueling availability. The refueling methods employed included cans, barrels, home refueling outfits, parking garage refueling facilities, mobile stations, hand carts and curb pumps. Only after robust markets for gasoline vehicles had been firmly established did the gasoline service station become the dominant refueling method. The present study reviews this history and draws analogies with current and future efforts to introduce hydrogen as a fuel for vehicles. These comparisons hold no predictive power; however, there is heuristic value in an historical review of the first successful and large-scale introduction of a vehicle fuel. From an energy policy perspective, these comparisons reinforce the importance of a long-term and portfolio approach to support for technology development and innovation

  13. The hydrogen refuelling plant in Madrid

    Energy Technology Data Exchange (ETDEWEB)

    Giron, E.; Saez, A.; Julia, A.

    2005-07-01

    Since the late days of spring 2003, a hydrogen refuelling station is operating in Madrid to provide fuel to a set of four FC-buses running in the frame of the European demonstration projects CUTE and CITYCELLS. This station is located at one of the EMT(1) bus depot premises. The station was designed and built for the EMT by the consortium 'esH2' composed by the industrial gases manufacturer Air Liquide Espana, the energy utility Gas Natural SDG and the oil company Repsol YPF. (Author)

  14. On the refuelling of large divertor experiments

    International Nuclear Information System (INIS)

    Staebler, A.; Haas, G.; Ott, W.; Speth, E.

    1976-01-01

    The use of fast hydrogen atoms, molecules and clusters for refuelling large divertor-experiments like ASDEX is investigated. Three criteria for the choice among the various methods are discussed. It is shown that clusters suffer from lack of penetration. Molecules, created by fragmentation of clusters, offer the advantage of plasma-like energy combined with appreciable penetration. Large penetration and high ionization efficiency can only be achieved at energies for above the plasma temperature with H 0 -atoms of several tens of keV

  15. Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank

    Science.gov (United States)

    Corletti, Michael M.; Lau, Louis K.; Schulz, Terry L.

    1993-01-01

    The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.

  16. Refueling strategy at the Budapest research reactor

    International Nuclear Information System (INIS)

    Hargitai, Timor

    1998-01-01

    Refueling strategy is very important for nuclear power plants and for highly utilized research reactors with power level in the megawatt range. New core design shall fulfill several demands and needs which can contradict each other sometimes. The loaded uranium quantity should assure the scheduled operation time (energy generation) and the maneuvering capability even at the end of the campaign. On the other hand the built in excess reactivity cannot be too high, because otherwise it would jeopardize the shutdown margin and reactor safety. Moreover the core arrangement should be optimum for in-core irradiation purposes and for the beam port experiments too. Sometimes this demand can be in contradiction with the desired burnup level. The achieved burnup level is very important from the fresh fuel consumption point of view, which has direct economic significance, however the generated spent fuel quantity is an important issue too. The refueling technique presented here allowed us at the Budapest Research Reactor to reach average burnup levels superseding 60%. (author)

  17. Refuelling: Swiss station will be semi-automated

    International Nuclear Information System (INIS)

    Fontaine, B.; Ribaux, P.

    1981-01-01

    The first semi-automated LWR refuelling machine in Europe has been supplied to the Leibstadt General Electric BWR in Switzerland. The system relieves operators of the boring and repetitive job of moving and accurately positioning the refuelling machine during fuelling operations and will thus contribute to plant safety. The machine and its mode of operation are described. (author)

  18. Control Room Tasks During Refueling in Ringhals 1 Nuclear Power Plant - Operator performance during refuelling outages

    International Nuclear Information System (INIS)

    Stroebeck, Einar; Olausson, Jesper; Van Gemst, Paul

    1998-01-01

    This paper discusses the performance and tasks of the operators in the control room during refuelling outages. Analyses of such events have, during the last years, shown that the risk for nuclear accidents is not negligible compared with the risk at higher reactor power levels. Some experts have the opinion that, due to mistakes during an outage, the risk for such accidents during the outage and other accidents later on during power operation is higher than in other plant situations. The high risk level is mainly a result of errors at maintenance actions and supervision of lining up of safety systems. Most of the control rooms in existing NPPs were designed more than 10 years ago. At that time the activities and the tasks for the operators were not very well understood. Procedures for refuelling and other activities during the outages were not described very well. Often the utility organisation for refuelling outages was not established at the start of the control room design. Experience from operation during many years has shown that the performance of operators can be improved in existing plant, and thus risks be reduced, by upgrading the control room. These issues have been studied as a part of the modernisation project for Ringhals 1, an ABB Atom BWR owned by Vattenfall AB in Sweden. The paper will describe the working model for upgrading the control room and important issues to take care of with respect to refuelling outages. The identified issues will be used as the input for improving control room philosophy and the individual technical systems. (authors)

  19. Risk assessment of LPG automotive refuelling facilities

    Energy Technology Data Exchange (ETDEWEB)

    Melchers, R.E. [University of Newcastle, Newcastle (Australia). Dept. of Civil, Surveying and Enviromental Engineering; Feutrill, W.R. [Wesfarmers Kleenheat Gas Pty. Ltd., Perth (Australia)

    2001-12-01

    Quantified risk analysis (QRA) was used for the revision of regulatory separation distances associated with medium size liquefied petroleum gas (LPG) refuelling facilities used in automotive service (gas) stations. Typically these facilities consist of a 7.5 kl pressure vessel, pump, pipework, dispensing equipment and safety equipment. Multi-tank installations are relatively uncommon. This paper describes the hazard scenarios considered, the risk analysis procedure and the selection and application of data for initiating events and for rates of failure of mechanical components and of the pressure vessel. Human errors and intervention possibilities were also considered. Because of the inapplicability of established consequence models and the relatively small scale of the facilities, a number of tests were performed to estimate flame length, flame impingement effects, ignition probabilities and the effectiveness of screening devices. (author)

  20. Hydrogen Refuelling Station Hamburg HafenCity

    Energy Technology Data Exchange (ETDEWEB)

    Hustadt, Daniel [Vattenfall Europe Innovation GmbH (Germany)

    2010-07-01

    Decoupling the growing road traffic and the related greenhouse gas emissions demand a major effort by research, OEMs as well as oil and energy companies. Above all the reduction of CO2-emissions is a growing need for climate protection. Bio fuels can help to reach those targets, however the available sources are not enough to guarantee a sustainable supply. Battery Electric Vehicles are today limited technically with regards to range and weight and will most likely be used in metropolitan regions. In this project the necessary infrastructure to refuel buses and cars of a bigger fleet will be installed. Doing so the prerequisite for using fuel cell based cars and buses as an alternative way of mobility is developed. The capability of new components for the productions, storage and distribution of larger amounts of hydrogen is shown. Additionally still existing potential optimizing on a technical and operational level shall be made available. (orig.)

  1. Refueling outage data collection and analysis

    International Nuclear Information System (INIS)

    Harshaw, K.; Quilliam, J.; Brinsfield, W.; Jeffries, J.

    1993-07-01

    This report summarizes the results of an EPRI project to compile an industry generic refueling outage database applicable to alternate (non-full-power) modes of shutdown conditions at nuclear power plants. The project team evaluated five outages at two BWR plants. They obtained data primarily from control room logs, outage schedules, incident reports, and licensee event reports. The team organized the data by outage segment and time line. Due to its small sample size, this study produced no conclusive results related to initiating event frequencies, equipment failure rates, or human reliability estimates during shutdown conditions. However, it pointed out the problems of brief or inconsistent recordkeeping. A too brief record results in difficulty determining if the root cause of an event was mechanical or the result of human performance. Retrieval of data can be difficult and labor-intensive. There is a clear need for better, more comprehensive documentation

  2. Gear failure of a PHWR refuelling machine

    International Nuclear Information System (INIS)

    Iorio, A.F.; Crespi, J.C.

    1986-01-01

    After ten year service in Atucha Nuclear Station a gear belonging to a pressurized heavy water reactor refuelling machine, failed. The gear box was used to transmit motion to the inlet-outlet heavy-water valve of that machine. Visual examination of the gear device revealed an absence of lubricant and several gear teeth were broken off at the root. The gear motion was transmitted from a speed-reducing device with controlled adjustable times in order to produce a right fitness of the valve closure. The main cause of gear failure was due to misalignment produced during assembly or in-service operation. It is suggested to control periodically the level of oil lubricant. (orig./IHOE) [de

  3. Regional Consumer Hydrogen Demand and Optimal Hydrogen Refueling Station Siting

    Energy Technology Data Exchange (ETDEWEB)

    Melendez, M.; Milbrandt, A.

    2008-04-01

    Using a GIS approach to spatially analyze key attributes affecting hydrogen market transformation, this study proposes hypothetical hydrogen refueling station locations in select subregions to demonstrate a method for determining station locations based on geographic criteria.

  4. Tracking of fission products release during refueling operations

    International Nuclear Information System (INIS)

    Agarwal, Sharad; Prajapat, M.K.; Vyas, Shyam; Hussain, S.A.

    2001-01-01

    It has been always observed that the release of fission products increase during refueling operations. At RAPP-3 and 4 an attempt has been made to follow-up the change in fission products activity release at each stage of refueling operation and quantification of concentrations of various radionuclides. This exercise was also extended to refueling operation of the channels containing suspected failed fuel. A level of FPNG ( 133 Xe) was observed to increase by a factor of about 10-40 during refueling of failed channel as compared to healthy channel. It can be concluded that by monitoring FPNG levels in exhaust status of the healthiness of spent fuel can be found out. This report discusses in detail the experiment conducted for this purpose. (author)

  5. Aerial Refueling For NATO’s Smart Defence Initiative

    Science.gov (United States)

    2012-04-01

    Rome: NATO Defense College, 2012, 148. 40 David A. Brown , "NATO Studying Development of Dedicated Refueling Unit Similar to Early Warning Force...accessed March 1, 2012). Brown , David A. "NATO Studying Development of Dedicated Refueling Unit Similar to Early Warning Force." Aviation Week...Aircraft. Coulsdon, Surrey: IHS Global Limited, 2011. Jennings, Gareth . "Nations Pool for NATO C-17A Fleet." Jane’s Defence Weekly, October 2008

  6. Image Dependent Relative Formation Navigation for Autonomous Aerial Refueling

    Science.gov (United States)

    2011-03-01

    and local variations of the Earth’s surface make a mathematical model difficult to create and use. The definition of an equipotential surface ...controlled with flight control surfaces attached to it. To refuel using this method, the receiver pilot flies the aircraft to within a defined refueling...I-frame would unnecessarily complicate aircraft navigation that, by definition, is limited to altitudes relatively close to the surface of the Earth

  7. Research on constellation refueling based on formation flying

    Science.gov (United States)

    Bo, Xu; Feng, Quansheng

    2011-06-01

    A new scheme for refueling satellite constellation is proposed in this paper. Compared with the traditional research, where the satellite refueling is implemented through spacecraft rendezvous and docking, the new pattern studied here is based on formation flying, and it is more feasible, safer and more reliable. On the grounds of the proposed pattern, two refueling strategies are studied. The first is called single supplier refueling (SSR) based on formation flying. In this scenario, one fuel-sufficient satellite called a supplier, departs from its parking orbit, and after a series of orbit maneuvers, arrives at the target constellation that consists of multiple fuel-deficient satellites called workers. It then transfers equal fuel to each worker within the prescribed mission time. The second strategy is called double suppliers refueling (DSR) based on formation flying. This time two suppliers take charge of refueling half of the workers respectively in the same way as SSR. Using a genetic algorithm, the orbit of a supplier with a minimum consumption of fuel can be obtained once the mission time is fixed. Simulation results indicate that DSR is superior to SSR and that this dominance will be more distinct as the number of workers increases and the mission time decreases.

  8. Refueling system with small diameter rotatable plugs

    International Nuclear Information System (INIS)

    Ritz, W.C.

    1987-01-01

    This patent describes a liquid-metal fastbreeder nuclear reactor comprising a reactor pressure vessel and closure head therefor, a reactor core barrel disposed within the reactor vessel and enclosing a reactor core having therein a large number of closely spaced fuel assemblies, and the reactor core barrel and the reactor core having an approximately concentric circular cross-sectional configuration with a geometric center in predetermined location within the reactor vessel. The improved refueling system described here comprises: a large controllably rotatable plug means comprising the substantial portion of the closure head, a reactor upper internals structure mounted from the large rotatable plug means. The large rotatable plug means has an approximately circular configuration which approximates the cross-sectional configuration of the reactor core barrel with a center of rotation positioned a first predetermined distance from the geometric center of the reactor core barrel so that the large rotatable plug means rotates eccentrically with respect to the reactor core barrel; a small controllably rotatable plug means affixed to the large rotatable plug means and rotatable with respect thereto. The small rotatable plug means has a center of rotation which is offset a second predetermined distance from the rotational center of the large rotatable plug means so that the small rotatable plug means rotates eccentrically with respect to the large rotatable plug means

  9. Minimizing or eliminating refueling of nuclear reactor

    Science.gov (United States)

    Doncals, Richard A.; Paik, Nam-Chin; Andre, Sandra V.; Porter, Charles A.; Rathbun, Roy W.; Schwallie, Ambrose L.; Petras, Diane S.

    1989-01-01

    Demand for refueling of a liquid metal fast nuclear reactor having a life of 30 years is eliminated or reduced to intervals of at least 10 years by operating the reactor at a low linear-power density, typically 2.5 kw/ft of fuel rod, rather than 7.5 or 15 kw/ft, which is the prior art practice. So that power of the same magnitude as for prior art reactors is produced, the volume of the core is increased. In addition, the height of the core and it diameter are dimensioned so that the ratio of the height to the diameter approximates 1 to the extent practicable considering the requirement of control and that the pressure drop in the coolant shall not be excessive. The surface area of a cylinder of given volume is a minimum if the ratio of the height to the diameter is 1. By minimizing the surface area, the leakage of neutrons is reduced. By reducing the linear-power density, increasing core volume, reducing fissile enrichment and optimizing core geometry, internal-core breeding of fissionable fuel is substantially enhanced. As a result, core operational life, limited by control worth requirements and fuel burnup capability, is extended up to 30 years of continuous power operation.

  10. Design tool for offgrid hydrogen refuelling systems for aerospace applications

    International Nuclear Information System (INIS)

    Troncoso, E.; Lapeña-Rey, N.; Gonzalez, M.

    2016-01-01

    Highlights: • A simulation tool for offgrid CPV-based hydrogen refuelling systems is presented. • Simulations of system configurations with specific UAS hydrogen demand scenarios. • Regarding system size & reliability the most critical components are the CPV array and batteries. • In terms of energy efficiency the most critical component is the electrolyser. - Abstract: To develop an environmentally acceptable refuelling solution for fuel cell-powered unmanned aerial systems (UASs) to operate in remote areas, hydrogen fuel must be produced on-site from renewable energy sources. This paper describes a Matlab-based simulation tool specifically developed to pre-design offgrid hydrogen refuelling systems for UAS applications. The refuelling system comprises a high concentrated PV array (CPV), an electrolyser, a hydrogen buffer tank and a diaphragm hydrogen compressor. Small composite tanks are also included for fast refuelling of the UAV platforms at any time during the year. The novel approach of selecting a CPV power source is justified on the basis of minimizing the system footprint (versus flat plat or low concentration PV), aiming for a containerized remotely deployable UAS offgrid refuelling solution. To validate the simulation tool a number of simulations were performed using experimental data from a prototype offgrid hydrogen refuelling station for UAVs developed by Boeing Research & Technology Europe. Solar irradiation data for a selected location and daily UAS hydrogen demands of between 2.8 and 15.8 Nm"3 were employed as the primary inputs, in order to calculate a recommended system sizing solution and assess the expected operation of the refuelling system across a given year. The specific energy consumption of the refuelling system obtained from the simulations is between 5.6 and 8.9 kW h_e per kg of hydrogen delivered to the UAVs, being lower for larger daily hydrogen demands. Increasing the CPV area and electrolyser size in order to supply higher

  11. Technical and economic analysis of hydrogen refuelling

    International Nuclear Information System (INIS)

    Nistor, Silviu; Dave, Saraansh; Fan, Zhong; Sooriyabandara, Mahesh

    2016-01-01

    Highlights: • Technical and economic models of a hydrogen station for vehicles refuelling. • Hydrogen demand from fuel cell electric vehicles modelled stochastically. • Study case based on a UK pilot project. • Operation of the H_2 station using combined energy from wind and power grid is preferred. • Return on investment of 5–10 years is possible for the hydrogen station. - Abstract: This paper focuses on technical and economic analysis of a hydrogen refilling station to provide operational insight through tight coupling of technical models of physical processes and economic models. This allows the dynamic relationships of the system to be captured and analysed to provide short/medium term analytical capability to support system design, planning, and financing. The modelling developed here highlights the need to closely link technical and economic models for technology led projects where technical capability and commercial feasibility are important. The results show that hydrogen fuel can be competitive with petrol on a GBP/KG basis if the return on investment period is over 10 years for PEM electrolysers and 5 for Alkaline electrolysers. We also show that subsidies on capital costs (as reflected by some R&D funding programs) make both PEM and Alkaline technologies cheaper than the equivalent price of petrol, which suggests more emphasis should be put on commercialising R&D funded projects as they have commercial advantages. The paper also shows that a combined wind and grid connected station is preferable so that a higher number of customers are served (i.e. minimum shortage of hydrogen).

  12. Preliminary design considerations for automatic refueling at N Reactor

    International Nuclear Information System (INIS)

    Quapp, W.J.; Yount, J.A.

    1985-01-01

    The Refueling Enhancement Program is an effort to upgrade and improve the N Reactor refueling operation. Primary goals of this effort are to reduce personnel exposure, reduce effluents to the environment, and, where possible, increase the refueling rate. Recent advances in available commercial robotics systems have prompted a look at automating the Charge/Discharge (C/D) operations. Current efforts will culminate in a conceptual design report (CDR) and accompanying economic and risk analysis in January 1986. Based on the results in that report, DOE will review the viability of the approach as a future capital project. Implementation of automation in existing plants raises questions regarding both the programmatic (how does one implement such an effort) and technical (what equipment is available; how will it be applied) concerns. This paper addresses both aspects

  13. Manufacturing Competitiveness and Supply Chain Analyses for Hydrogen Refueling Stations

    Energy Technology Data Exchange (ETDEWEB)

    Mayyas, Ahmad T [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Garland, Nancy [U.S. Department of Energy

    2018-04-27

    This slide deck was presented in the monthly FCTO webinar series (May 2017). The goal of this presentation was to share our latest results and remarks on the manufacturing competitiveness analysis of the hydrogen refueling stations (HRS). Manufacturing cost models were developed for major systems in the HRS such as compressors, storage tanks, chillers, heat exchangers, and dispensers. In addition to the cost models, we also discussed important remarks from our analysis for the international trade flows and global supply chain for the hydrogen refueling stations. The last part of the presentation also highlights effect of economies of scale and high production volumes on lowering the cost of the hydrogen at the pump.

  14. Structural Analysis of Advanced Refueling Machine of APR1400

    International Nuclear Information System (INIS)

    Cho, J. R.; Kim, Y. H.; Park, B. T.; Park, J. B.; Jung, J. H.

    2007-01-01

    The Refueling Machine (RM) consists of two structural parts of bridge and trolley. The bridge structure is approximately 8.5 m long and 5 m wide and is primarily composed of two deep wide flange sections spanning the rector area at the operating level. The trolley is mounted on wheels that roll on the rails of the bridge. Vertical movements of trolley and bridge are restricted by guide rollers. In this paper, dynamic and structural analyses based on the earthquake spectrum are carried out to verify the structural integrity of advanced refueling machine. It is done by 3-dimensional finite element analysis using ANSYS software

  15. Hyapproval : final handbook for approval of hydrogen refuelling stations

    NARCIS (Netherlands)

    Wurster, R.; Landinger, H.; Machens, C.; Allidières, L.; Molag, M.; Barron, J.; Reijalt, M.; Hill, H.J.

    2006-01-01

    HyApproval is an EC co-financed Specific Targeted Research Project (STREP) to develop a Handbook facilitating the approval of Hydrogen Refuelling Stations (HRS). The project, started in October 2005, will be performed over 24 months by a balanced partnership including 25 partners from industry, SMEs

  16. Integrated refuelling activity service; Servicio integrado de actividades de recarga

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Valcarcel, M.; Lopez Garcia, J.L.

    2010-07-01

    Refuelling outages at nuclear power plants are subject to demanding improvement criteria in each and every one of the activities scheduled. In this article, the advantages of this general service performed by UTE-TWE for Asco and Vandellos II nuclear power plants, and their results and learned lessons are presented. (Author)

  17. H2USA: Siting Refueling Stations in the Northeast

    Energy Technology Data Exchange (ETDEWEB)

    Melaina, Marc W [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Muratori, Matteo [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Zuboy, Jarett [Consultant; Ellis, Steve [Honda

    2017-11-01

    To achieve cost-effective deployment of both fuel cell electric vehicles (FCEVs) and hydrogen stations, the number of vehicles and public stations must grow together in areas of highest demand. This fact sheet introduces two advanced modeling tools and presents preliminary analysis of the hydrogen refueling station locations needed to support early consumer demand for FCEVs in the Northeast United States. United States.

  18. Refueling outage services in Spanish Nuclear Power Plants

    International Nuclear Information System (INIS)

    Landete, J. L.; Soto, M.; Nunuez, A.

    2007-01-01

    DOMINGUIS Group, through its 75 years of business development, has positioned as the Spanish leader Group in Services for the Nuclear Energy and Petrochemical Sectors. In this article, we present the most significant services summary that, through the companies that constitute DOMINGUIS Group, we have developed in Refueling Outage in Spanish Nuclear Power Plants. (Author)

  19. 40 CFR 86.152-98 - Vehicle preparation; refueling test.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false Vehicle preparation; refueling test... PROGRAMS (CONTINUED) CONTROL OF EMISSIONS FROM NEW AND IN-USE HIGHWAY VEHICLES AND ENGINES Emission Regulations for 1977 and Later Model Year New Light-Duty Vehicles and New Light-Duty Trucks and New Otto-Cycle...

  20. Study of Arkansas Nuclear One-1 13th refueling outage

    International Nuclear Information System (INIS)

    Hashiba, Takashi

    1997-01-01

    Recently performance of nuclear power plants in the USA has improved remarkably. Their average automatic shutdown rate has been sharply dropping, although it is still higher than that in Japan, and their average capacity factor has become higher than that in Japan in recent years. One of the main contributors is an extension of the operational period, and another is a shortening of refueling-outage time. It is considerably difficult to have accomplished both the improvement of plant reliability and shortening of refueling-outage time because their refueling outage corresponds to our periodical inspection which is central to maintenance activities in Japanese plants. In order to learn how they have been achieved, a visit to Arkansas Nuclear One-1 (ANO-1) which obtained the top-class result of SALP (Systematic Assessment of Licensee Performance) performed by the Nuclear Regulatory Commission was planned and study of their 13th refueling outage was carried out. Their achievements result from performance-base maintenance and on-line maintenance, based on a proper preventive maintenance program, and untiring efforts of efficiency improvement, represented by the introduction of several on-line systems. And the reason behind this is severe competition concerning power generation cost reduction. (author)

  1. Study of Arkansas Nuclear One-1 13th refueling outage

    Energy Technology Data Exchange (ETDEWEB)

    Hashiba, Takashi [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

    1997-09-01

    Recently performance of nuclear power plants in the USA has improved remarkably. Their average automatic shutdown rate has been sharply dropping, although it is still higher than that in Japan, and their average capacity factor has become higher than that in Japan in recent years. One of the main contributors is an extension of the operational period, and another is a shortening of refueling-outage time. It is considerably difficult to have accomplished both the improvement of plant reliability and shortening of refueling-outage time because their refueling outage corresponds to our periodical inspection which is central to maintenance activities in Japanese plants. In order to learn how they have been achieved, a visit to Arkansas Nuclear One-1 (ANO-1) which obtained the top-class result of SALP (Systematic Assessment of Licensee Performance) performed by the Nuclear Regulatory Commission was planned and study of their 13th refueling outage was carried out. Their achievements result from performance-base maintenance and on-line maintenance, based on a proper preventive maintenance program, and untiring efforts of efficiency improvement, represented by the introduction of several on-line systems. And the reason behind this is severe competition concerning power generation cost reduction. (author)

  2. Optimal refueling principle of research and test reactors and its application

    International Nuclear Information System (INIS)

    Peng Feng; Sun Shouhua; Bu Yongxi

    1993-01-01

    Based on basic formula for core refueling, the optimal refueling principle for cores with fuel assemblies of different burnup are suggested. Some conclusions derived from this principle are given. Calculation formula for different refueling scheme and computation programme are derived and used for the HFETR typical core loading with different refueling scheme. With the suggested core fuel consuming index, core fuel managements of 24 cycles in 10 years operation of HFETR were analyzed. Results show that the application of optimal refueling principle can greatly save the fuel consuming. Direction of HFETR core fuel management research was also di cussed

  3. Potential risk of a criticality event during refuelling

    Energy Technology Data Exchange (ETDEWEB)

    Laurioux, V.; Deschamps, P

    2003-01-01

    Following a core unloading due to an unscheduled shutdown during the cycle of Dampierre unit 4, the plant operator had to operate the refuelling in its previous configuration. During this operation, the fuel assembly concerned by loading step no. 25 was left in the fuel building and the assembly for the following step, no. 26, was placed in the reactor vessel instead of the previous one, causing an irregularity in core pattern only detected at step no. 139. At that point, the refuelling machine operator realized that he was handling an assembly equipped with its rod cluster, whereas according to his handling sheet, the assembly should not be equipped with. Thanks to the favourable conditions (primary system boron concentration = 2345 ppm and cycle burn-up = 2 GWj/tU), the core remained subcritical. However, the incident analysis revealed a potential criticality risk under less favourable circumstances, i.e. refuelling with fresh 1. cycle fuel assemblies and a primary system boron concentration at the lower limit of the range allowed by the Technical Operating Specifications (2000 ppm). Moreover, further studies have shown that the two neutron source range channels (SRC) are able to provide a count rate (reflecting neutron flux) but would not detect a local increase in reactivity under refuelling conditions (normal or defective), unless a reactive pattern was formed in the immediate vicinity of one of the two channels. However, if the criticality is reached, the SRCs are able to diagnose the critical state from the significant power level of 0.1% rated power. The human error that had led to the administrative validation of a fuel handling step that had not been physically carried out highlighted both the fragility of organizational lines of defence and the inadequacy of I and C systems with regard to technical in-depth defence lines. Following these observations, and beyond the preventive measures supposed to limit the occurrence of a divergence during refuelling

  4. Customer exposure to gasoline vapors during refueling at service stations.

    Science.gov (United States)

    Hakkola, M A; Saarinen, L H

    2000-09-01

    Gasoline is a volatile complex mixture of hydrocarbon compounds that is easily vaporized during handling under normal conditions. Modern reformulated gasoline also contains oxygenates to enhance octane number and reduce ambient pollution. This study measured the difference in the exposure of customers to gasoline and oxygenate vapors during refueling in service stations with and without vapor recovery systems. Field measurements were carried out at two self-service stations. One was equipped with Stage I and the other with Stage II vapor recovery systems. At Stage I stations there is vapor recovery only during delivery from road tanker, and at Stage II stations additional vapor recovery during refueling. The exposure of 20 customers was measured at both stations by collecting air samples from their breathing zone into charcoal tubes during refueling with 95-octane reformulated gasoline. Each sample represented two consecutive refuelings. The samples were analyzed in the laboratory by gas chromatography using mass-selective detection for vapor components. The Raid vapor pressure of gasoline was 70 kPa and an oxygen content 2 wt%. Oxygenated gasoline contained 7 percent methyl tert-butyl ether (MtBE) and 5 percent methyl tert-amyl ether (MtAE). The geometric mean concentrations of hydrocarbons (C3-C11) in the customers' breathing zone was 85 mg/m3 (range 2.5-531 mg/m3) at the Stage I service station and 18 mg/m3 (range service station. The geometric mean of the exposure of customers to MtBE during refueling at the Stage I service station was 15.3 mg/m3 (range 1.8-74 mg/m3), and at the Stage II service station 3.4 mg/m3 (range 0.2-16 mg/m3). The differences in exposure were statistically significant (p station. The measurements were done on consecutive days at the various service stations. The temperature ranged from 10 to 17 degrees C, and wind velocity was 2-4 m/s. The climatic conditions were very similar on the measurement days. Based on this study it was found

  5. Performance of a rapidly-refuelable aluminum-air battery

    Science.gov (United States)

    Levy, D. J.; Hollandsworth, R. P.; Gonzales, E. M.; Littauer, E. L.

    The Al-air battery is being developed to provide an electric vehicle with conventional automobile performance. A rapidly-refuelable, 6-cell battery (200-sq cm electrodes) was evaluated. RX-808 aluminum anodes and air cathodes were used with a flowing alkaline electrolyte. Peak power was found to increase with temperature, decrease with aluminate concentration and be unaffected by electrolyte flow. The best performance was 5.28 kW/sq m peak power density, 2.08 kWh/kg Al energy density and 80 percent coulombic efficiency. Anode refueling is rapid and 100 percent utilization is achieved. Additional evaluation included cathode catalysts, a thermal balance and monitoring electrolyte composition.

  6. Refueling device for a nuclear reactor with fast neutrons

    International Nuclear Information System (INIS)

    Artemev, L.N.; Vitalevitsch, K.V.

    1978-01-01

    The refueling device has got a drum-shaped cartridge containing cells for unirradiated fuel assemblies and control rods as well as a grab for manipulation. The cells for the fuel assemblies are identical with those for the control rods. For the control rods in stock and those on the way from the drum-shaped magazine to the refueling mechanism there are provided cup-shaped casings (adapters) adapting their ends to the dimensions of the fuel assemblies. The casing is clamped to an annular tee-slot below the top by means of a collet. By this means fuel assemblies as well as control rods can be handled with the grab. By means of a stop on the grab the casing can be detached from the control rod. (DG) [de

  7. Television alignment of mast assembly in refueling of nuclear reactor

    International Nuclear Information System (INIS)

    Kaufmann, J.W.; Swidwa, K.J.; Hornak, L.P.

    1990-01-01

    This patent describes the refueling of a nuclear reactor having component assemblies of at least one type and being disposed in a pit in a containment under water, the refueling being carried out with a mast movable axially and circumferentially for raising and lowering the component assemblies, a mechanism, connected to an end of the mast, cooperative with the mast, for engaging a component assembly to be raised by the mast, a television camera, and a television monitor having an image-reference indication, the mechanism being connected to the mast movable with the mast; the method of positioning the mechanism to engage the component assembly appropriately for raising and lowering. It comprises: mounting the camera on the mechanism movable therewith, suspending the mast in the water of the pit with the mechanism extending from the end of the mast in the pit in position to engage the component assembly

  8. Business fleet refueling assessment. Final report, March 1992-November 1992

    International Nuclear Information System (INIS)

    Chaudier, A.

    1993-01-01

    The report investigates refueling characteristics and capabilities for the light-duty market sector, particularly business automobile fleets. It develops a profile of the characteristics of light-duty and automobile business fleets in 22 designated non-attainment areas, as well as Pittsburgh and Salt Lake City. Reliable data on these subjects will enable better analysis of the market potential for natural gas in the surveyed areas

  9. On the Drag Effect of a Refuelling Pellet

    DEFF Research Database (Denmark)

    Chang, Tinghong; Michelsen, Poul

    1981-01-01

    A refueling pellet is subjected mainly to two kinds of drags: (1) inertial drag caused by the motion of the pellet relative to the surrounding plasma, and (2) ablation drag caused by an uneven ablation rate of the front and the rear surface of the pellet in an inhomogeneous plasma. Computational ...... results showed that for reasonable combinations of pellet size and injection speed, the drag effect is hardly detectable for plasma conditions prevailing in current large tokamaks....

  10. RBMK full scope simulator gets virtual refuelling machine

    International Nuclear Information System (INIS)

    Khoudiakov, M.; Slonimsky, V.; Mitrofanov, S.

    2006-01-01

    The paper describes a continuation of efforts of an international Russian-Norwegian joint team to drastically increase operational safety during the refuelling process of an RBMK-type reactor by implementing a training simulator based on an innovative Virtual Reality (VR) approach. During the preceding stage of the project a display-based simulator was extended with VR models of the real Refueling Machine (RM) and its environment in order to improve both the learning process and operation's effectiveness. The simulator's challenge is to support the performance (operational activity) of RM operational staff firstly and to take major part in developing basic knowledge and skills as well as to keep skilled staff in close touch with the complex machinery of the Refueling Machine. At the given 2nd stage the functional scope of the VR-simulator was greatly enhanced - firstly, by connecting to the RBMK-unit full-scope simulator, and, secondly, by a training program and simulator model upgrade. (author)

  11. Automated Aerial Refueling Hitches a Ride on AFF

    Science.gov (United States)

    Hansen, Jennifer L.; Murray, James E.; Bever, Glenn; Campos, Norma V.; Schkolnik, Gerard

    2007-01-01

    The recent introduction of uninhabited aerial vehicles [UAVs (basically, remotely piloted or autonomous aircraft)] has spawned new developments in autonomous operation and posed new challenges. Automated aerial refueling (AAR) is a capability that will enable UAVs to travel greater distances and loiter longer over targets. NASA Dryden Flight Research Center, in cooperation with the Defense Advanced Research Projects Agency (DARPA), the Naval Air Systems Command (NAVAIR), the Naval Air Force Pacific Fleet, and the Air Force Research Laboratory, rapidly conceived and accomplished an AAR flight research project focused on collecting a unique, high-quality database on the dynamics of the hose and drogue of an aerial refueling system. This flight-derived database would be used to validate mathematical models of the dynamics in support of design and analysis of AAR systems for future UAVs. The project involved the use of two Dryden F/A-18 airplanes and an S-3 hose-drogue refueling store on loan from the Navy. In this year-long project, which was started on October 1, 2002, 583 research maneuvers were completed during 23 flights.

  12. Engineering study of frequent refueling for improved uranium utilization in pressurized water reactors

    International Nuclear Information System (INIS)

    Bernstein, I.

    1981-05-01

    The most practical alternative to annual refueling appeared to be semiannual refueling, with a short midyear refueling-only outage scheduled during minimum power demand and an annual outage during which maintenance outage tasks would be performed. A method for economic evaluation of frequent refueling was developed using fuel loading requirements, refueling frequency, replacement power costs and the price of uranium oxide as parameters and the economics evaluated with the costs anticipated for the year 1995. It was determined that to obtain breakeven energy costs, the extra semiannual refueling outage would have to be accomplished in six to nine days for most plants. Although it could not practicably be reduced to that level, proposed changes to arrangement, procedures and equipment indicated that an outage of from eleven to thirteen days was possible. Total cost of implementing these changes is estimated at less than 4% of the overall physical plant cost. This cost can be justified based on the time saved during refueling outages over the reactor lifetime. These changes were generally defined while a detailed design review was made of a fuel-handling system which utilizes two cantilever-supported refueling machines and two transfer systems, allowing independent and simultaneous handling of two fuel assemblies during the refueling sequence. A review of the critical path annual maintenance items indicated that these items would probably control the length of the annual refueling outage

  13. Development and operating performance of the refuelling machine of the Fugen

    International Nuclear Information System (INIS)

    Kaneko, Jun; Kasai, Yoshimitsu; Takeshita, Norito; Ohta, Takeo

    1985-01-01

    In the advanced thermal reactor ''Fugen'' power station, with the refuelling machine the fuel replacement during operation is made through the reactor bottom. Its design was started in 1967 and up to 1975 various tests were conducted. Fugen's refuelling machine has thus been used from the initial fuel loading in 1978 and handled so far about 1300 fuel assemblies in seven times of the refuelling. In the stage of Fugen operation there occurred failure of the grab drive due to crud, etc. At present, with such troubles all eliminated, the refuelling machine is in steady operation with proper maintenance. The results with Fugen's refuelling machine are reflected in the development of the refuelling machine for the demonstration ATR. (Mori, K.)

  14. Development and implementation of full-automatic supervision and control programme for CEFR refueling control system

    International Nuclear Information System (INIS)

    Zhu Hao; Dong Shengguo; Ma Hongsheng; Zhao Lixia

    2011-01-01

    In order to make the process of CEFR refueling more convenient and reliable, the computer supervision and control system was designed according to the CEFR refueling technology. Meanwhile, the supervision and control function and database function were developed on the basis of KingView and SQL Server2000. The fuel of reactor core was fully loaded by the system, and full-automation of CEFR refueling process was implemented. (authors)

  15. Status of small reactor designs without on-site refuelling

    International Nuclear Information System (INIS)

    2007-01-01

    There is an ongoing interest in member states in the development and application of small and medium sized reactors (SMRs). In the near term, most new NPPs are likely to be evolutionary designs building on proven systems while incorporating technological advances and often the economics of scale, resulting from the reactor outputs of up to 1600 MW(e). For the longer term, the focus is on innovative designs aiming to provide increased benefits in the areas of safety and security, non-proliferation, waste management, resource utilization and economy, as well as to offer a variety of energy products and flexibility in design, siting and fuel cycle options. Many innovative designs are reactors within the small-to-medium size range, having an equivalent electric power less than 700 MW(e) or even less than 300 MW(e). A distinct trend in design and technology development, accounting for about half of the SMR concepts developed worldwide, is represented by small reactors without on-site refuelling. Such reactors, also known as battery-type reactors, could operate without reloading and shuffling of fuel in the core over long periods, from 5 to 25 years and beyond. Upon the advice and with the support of IAEA member states, within its Programme 1 'Nuclear Power, Fuel Cycle, and Nuclear Science', the IAEA provides a forum for the exchange of information by experts and policy makers from industrialized and developing countries on the technical, economic, environmental, and social aspects of SMRs development and implementation in the 21st century, and makes this information available to all interested Member States by producing status reports and other publications dedicated to advances in SMR technology. The objective of this report is to provide Member States, including those just considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, with a balanced and objective information on important development trends and

  16. Liquefied petroleum gas cold burn sustained while refueling a car.

    Science.gov (United States)

    Scarr, Bronwyn; Mitra, Biswadev; Maini, Amit; Cleland, Heather

    2010-02-01

    There have been few cases of cold burn related to the exposure of liquid petroleum gas (LPG). We present the case of a young woman exposed to LPG while refueling her car who sustained partial thickness burns to the dorsum of her hand. Contact with LPG leaking from a pressurized system causes tissue damage because of cold injury. Immediate management of LPG is extrapolated from the management of frostbite. The increasing use of LPG mandates an awareness of prevention strategies and management principles in the setting of adverse events.

  17. Some novel on-power refuelling features of CANDU stations

    International Nuclear Information System (INIS)

    Erwin, D.; Pendlebury, B.; Watson, J.F.; Welch, A.C.

    1976-01-01

    Part A of the paper describes the reasons for, and advantages resulting from, the use of flow assisted refuelling in the CANDU type nuclear reactors at the Pickering Generating Station. A separate fuel handling system is used for each reactor unit, as distinct from the system employed at the Bruce Generating station, where the fuel handling system is shared among several units. Part B of the paper describes some of the advantages of the shared concept with particular emphasis on the availability of the fuel handling system. (author)

  18. Insights from Hydrogen Refueling Station Manufacturing Competitiveness Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mayyas, Ahmad

    2015-12-18

    In work for the Clean Energy Manufacturing Analysis Center (CEMAC), NREL is currently collaborating with Great Lakes Wind Network in conducting a comprehensive hydrogen refueling stations manufacturing competitiveness and supply chain analyses. In this project, CEMAC will be looking at several metrics that will facilitate understanding of the interactions between and within the HRS supply chain, such metrics include innovation potential, intellectual properties, learning curves, related industries and clustering, existing supply chains, ease of doing business, and regulations and safety. This presentation to Fuel Cell Seminar and Energy Exposition 2015 highlights initial findings from CEMAC's analysis.

  19. Lainsa refueling specific services. Ideas of an evolution

    International Nuclear Information System (INIS)

    Soto Tomas, M.

    2010-01-01

    The knowledge evolution, in relation to works to develop in Refueling, related to the Cleaning and Decontamination, changed from almost total ignorance to be a reality, thanks personnel support and external organizations, already knowledgeable of the same, and to the human team effort highly involved in the fulfillment of the management development. We search where to find knowledge and we did it. We had ideas and we became them truth. The evolutionary process was positive. Some stages, equipment and developed services are commented, which allow us to offer High Quality Services and in agreed time term, especially during c ritical path . (Author)

  20. CLEO: A knowledge-based refueling assistant at FFTF

    International Nuclear Information System (INIS)

    Smith, D.E.; Kocher, L.F.; Seeman, S.E.

    1985-07-01

    CLEO is computer software system to assist in the planning and performance of the reactor refueling operations at the Fast Flux Test Facility. It is a recently developed application of artificial intelligence software with both expert systems and automated reasoning aspects. The computer system seeks to organize the sequence of core component movements according to the rules and logic used by the expert. In this form, CLEO has aspects which tie it to both the expert systems and automated reasoning areas within the artificial intelligence field

  1. Optimal Refueling Pattern Search for a CANDU Reactor Using a Genetic Algorithm

    International Nuclear Information System (INIS)

    Quang Binh, DO; Gyuhong, ROH; Hangbok, CHOI

    2006-01-01

    This paper presents the results from the application of genetic algorithms to a refueling optimization of a Canada deuterium uranium (CANDU) reactor. This work aims at making a mathematical model of the refueling optimization problem including the objective function and constraints and developing a method based on genetic algorithms to solve the problem. The model of the optimization problem and the proposed method comply with the key features of the refueling strategy of the CANDU reactor which adopts an on-power refueling operation. In this study, a genetic algorithm combined with an elitism strategy was used to automatically search for the refueling patterns. The objective of the optimization was to maximize the discharge burn-up of the refueling bundles, minimize the maximum channel power, or minimize the maximum change in the zone controller unit (ZCU) water levels. A combination of these objectives was also investigated. The constraints include the discharge burn-up, maximum channel power, maximum bundle power, channel power peaking factor and the ZCU water level. A refueling pattern that represents the refueling rate and channels was coded by a one-dimensional binary chromosome, which is a string of binary numbers 0 and 1. A computer program was developed in FORTRAN 90 running on an HP 9000 workstation to conduct the search for the optimal refueling patterns for a CANDU reactor at the equilibrium state. The results showed that it was possible to apply genetic algorithms to automatically search for the refueling channels of the CANDU reactor. The optimal refueling patterns were compared with the solutions obtained from the AUTOREFUEL program and the results were consistent with each other. (authors)

  2. Modeling Hydrogen Refueling Infrastructure to Support Passenger Vehicles †

    Directory of Open Access Journals (Sweden)

    Matteo Muratori

    2018-05-01

    Full Text Available The year 2014 marked hydrogen fuel cell electric vehicles (FCEVs first becoming commercially available in California, where significant investments are being made to promote the adoption of alternative transportation fuels. A refueling infrastructure network that guarantees adequate coverage and expands in line with vehicle sales is required for FCEVs to be successfully adopted by private customers. In this paper, we provide an overview of modelling methodologies used to project hydrogen refueling infrastructure requirements to support FCEV adoption, and we describe, in detail, the National Renewable Energy Laboratory’s scenario evaluation and regionalization analysis (SERA model. As an example, we use SERA to explore two alternative scenarios of FCEV adoption: one in which FCEV deployment is limited to California and several major cities in the United States; and one in which FCEVs reach widespread adoption, becoming a major option as passenger vehicles across the entire country. Such scenarios can provide guidance and insights for efforts required to deploy the infrastructure supporting transition toward different levels of hydrogen use as a transportation fuel for passenger vehicles in the United States.

  3. Options for shortening nuclear power plant refueling outages

    International Nuclear Information System (INIS)

    Kastl, H.

    2001-01-01

    Deregulation of the European electricity market on 01.01.1999 forced a large number of electric utilities- especially nuclear power plant operators - to find ways of drastically cutting down their costs in order to be able to compete successfully within the new market environment. Nuclear power plants currently in operation mainly have three potential ways of reducing their power generating costs: by increasing plant availability, reducing fuel costs and cutting down operating costs. The optimization of plant refueling outages offers considerable potential for enhancing plant availability, but also helps bring down operating costs by reducing expenditure on maintenance. In order to optimize an outage in terms of its duration and costs, a variety of approaches are possible - all of which, however, involve certain key factors such as good organization, planning, logistics and control, improvement of equipment and tools, as well as motivation of personnel. Another aspect is the introduction of innovative technologies. In the last few years, such technologies have frequently enabled maintenance effort to be reduced, thus saving considerable time, and have also resulted in a need for fewer personnel to carry out the work, thus reducing radiation exposure. In many instances they have also improved the quality of work and outage performance as a whole. The paper uses recent examples to show how innovative technologies can contribute to-wards reducing nuclear plant maintenance costs and shorten the duration of refueling out-ages. (author)

  4. BWR Servicing and Refueling Improvement Program: Phase I summary report

    Energy Technology Data Exchange (ETDEWEB)

    Perry, D.R.

    1978-09-01

    Under the U.S. Department of Energy sponsorship, General Electric Co. (GE) undertook a study of boiling water reactor (BWR) refueling outages for the purpose of recommending the development and demonstration of critical path time savings improvements. The Tennessee Valley Authority (TVA) joined the study as a subcontractor, providing monitoring assistance and making the Browns Ferry Site available for improvement demonstrations. Agreement was also reached with Georgia Power Co., Power Authority of the State of New York, and Commonwealth Edison Co. for monitoring and data collection at Hatch 1, FitzPatrick, and Quad Cities 1 nuclear plants, respectively. The objective was to identify, develop, and demonstrate improved refueling, maintenance, and inspection procedures and equipment. The improvements recommended in this study are applicable to BWR nuclear plants currently in operation as well as those in the design and construction phases. The recommendations and outage information can be used as a basis to plan and conduct the first outages of new plants and to improve the planning and facilities of currently operating plants. Many of the recommendations can readily be incorporated in plants currently in the design and construction phases as well as in the design of future plants. Many of these recommended improvements can be implemented immediately by utilities without further technical development.

  5. Fire Protection Engineering Design Brief Template. Hydrogen Refueling Station.

    Energy Technology Data Exchange (ETDEWEB)

    LaFleur, Angela Christine [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Muna, Alice Baca [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Groth, Katrina M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    Building a hydrogen infrastructure system is critical to supporting the development of alternate- fuel vehicles. This report provides a methodology for implementing a performance-based design of an outdoor hydrogen refueling station that does not meet specific prescriptive requirements in NFPA 2, The Hydrogen Technologies Code . Performance-based designs are a code-compliant alternative to meeting prescriptive requirements. Compliance is demonstrated by comparing a prescriptive-based fueling station design with a performance-based design approach using Quantitative Risk Assessment (QRA) methods and hydrogen risk assessment tools. This template utilizes the Sandia-developed QRA tool, Hydrogen Risk Analysis Models (HyRAM), which combines reduced-order deterministic models that characterize hydrogen release and flame behavior with probabilistic risk models to quantify risk values. Each project is unique and this template is not intended to account for site-specific characteristics. Instead, example content and a methodology are provided for a representative hydrogen refueling site which can be built upon for new hydrogen applications.

  6. BWR Servicing and Refueling Improvement Program: Phase I summary report

    International Nuclear Information System (INIS)

    Perry, D.R.

    1978-09-01

    Under the U.S. Department of Energy sponsorship, General Electric Co. (GE) undertook a study of boiling water reactor (BWR) refueling outages for the purpose of recommending the development and demonstration of critical path time savings improvements. The Tennessee Valley Authority (TVA) joined the study as a subcontractor, providing monitoring assistance and making the Browns Ferry Site available for improvement demonstrations. Agreement was also reached with Georgia Power Co., Power Authority of the State of New York, and Commonwealth Edison Co. for monitoring and data collection at Hatch 1, FitzPatrick, and Quad Cities 1 nuclear plants, respectively. The objective was to identify, develop, and demonstrate improved refueling, maintenance, and inspection procedures and equipment. The improvements recommended in this study are applicable to BWR nuclear plants currently in operation as well as those in the design and construction phases. The recommendations and outage information can be used as a basis to plan and conduct the first outages of new plants and to improve the planning and facilities of currently operating plants. Many of the recommendations can readily be incorporated in plants currently in the design and construction phases as well as in the design of future plants. Many of these recommended improvements can be implemented immediately by utilities without further technical development

  7. 40 CFR 86.1825-08 - Durability demonstration procedures for refueling emissions.

    Science.gov (United States)

    2010-07-01

    ..., statistical analyses, additional data, or other information which is relevant to the decision. The... Durability demonstration procedures for refueling emissions. This section applies to 2008 and later model...-duty rules as allowed under the provisions of § 86.1801-01(c)(1) which are subject to refueling loss...

  8. Plasma density measurements on refuelling by solid hydrogen pellets in a rotating plasma

    International Nuclear Information System (INIS)

    Joergensen, L.W.; Sillesen, A.H.

    1978-01-01

    The refuelling of a plasma by solid hydrogen pellets situated in the plasma is investigated. Nearly half of the pellet material is evaporated and seems to be completely ionized, resulting in an increase of the amount of plasma equivalent to one third of the total amount of plasma without refuelling. The gross behaviour of the plasma is not changed. (author)

  9. The Feasibility of Pellet Re-Fuelling of a Fusion Reactor

    DEFF Research Database (Denmark)

    Chang, Tinghong; Jørgensen, L. W.; Nielsen, P.

    1980-01-01

    The feasibility of re-fuelling a fusion reactor by injecting pellets of frozen hydrogen isotopes is reviewed. First a general look is taken of the dominant energy fluxes received by the pellet, the re-fuelling rate required and the relation between pellet size, injection speed and frequency...

  10. The application of AI-based refueling control system to the Fugen NPP

    International Nuclear Information System (INIS)

    Maeda, Koichi; Nakamura, Shinji; Kawasaki, Noboru; Nanko, Takashi; Nishimura, Hiroshi; Tanaka, Koichi

    1996-01-01

    In a refueling operation of the Advanced Thermal Reactor Fugen, it is essential to precisely handle fuel assemblies to guarantee quality and from the standpoint of safety guard. In order to plan and execute efficient operations, knowledge of experienced operators based on experiences is required. Therefore, an automatic control system based on the Artificial Intelligence (AI) technology has been developed, and has been put into operation in actual refueling operations. This system prepares an optimum refueling plan, controls the fuel handling facilities by that plan, displays and prints out the history of transfer and storage of items by automatically sampled data on a work station, a network to express fuel handling facilities and operational rules acquired through operating experiences. The development of this system has made it possible to optimize refueling schedule, save control labor of items and improve reliability of refueling. Firstly the development started the off-line system that prepares optimum refueling plan and gives to the operator step by step instructions for operation, secondly developed the on-line system that automatically controls facilities by that plan. The development of this system started in 1989, the off-line system has been put into practical operation in the 17th refueling in 1991, the 22nd (12th annual inspection) refueling in 1995 has been done by using the on-line system automatically

  11. 1200 FPD refuelling simulation of RUFIC fuel in a CANDU 6 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Soon Young; Jeong, Chang Joon; Min, Byung Joo; Suk, Ho Chun

    2001-07-01

    The refuelling strategy of RUFIC (Recovered Uranium Fuel in CANDU) fuel as a high-burnup fuel for a CANDU 6 reactor is studied to determine the achievable operation characteristics of the fuel and reactor. In this study, three refuelling schemes of 4-, 2-, and 3-bundle shift for 0.92 w/o RUFIC fuel in an CANDU 6 reactor were individually evaluated through 1200 FPD(Full Power Day)refuelling simulaltions where the 0.92 w/o RUFIC is equivalent to CANFLEX 0.9 w/o SEU(Slightly Enriched Uranium) in reactivity and burnup respects. The computer code system used for this study is WIMS-AECL/DRAGON/RFSP. The results simulated for the case of 4-bundle shift refueling scheme shows that the peak maximum channel power and peak maximum CPPF(Channel Power Peaking Factor)of 7228 kW and 1.175, respectively, seems too high to maintain the available operating margins, because some data of the maximum channel power exceed the operating limit(7070 kW based on the Technical Specifications of Wolsong 3 and 4 Units). Whereas, the results simulated for the case of 2-bundle shift refuelling scheme shows that sufficient operating margin could be secured where the peak maximum channel power and peak maximum CPPF were 6889 kW and 1.094, respectively. However, the channel refuelling rate (channels/day) of the 2-bundle shift refuelling scheme is twice that of the 4-bundle shift refuelling scheme, and hence the 2-bundle shift refuelling would not be an economical refuelling scheme for the RUFIC fuel bundles. Therefore, a 3-bundle shift refuelling scheme for the RUFIC fuel in CANDU 6 reactor was also studied by the 1200 FPD refuelling simulation. As a result, it is found that all the operating parameters in the 3-bundle shift case are achivable for the CANDU 6 reactor operation, and the channel refuelling rate of 2.88 channels/day seems to be attractive compared to the refuelling rate of 4.32 channels/day in the 2-bundle shift case.

  12. New selection criteria for channel refueling of a Candu-6 reactor: introduction to floppy rules

    International Nuclear Information System (INIS)

    Brissette, D.

    2001-01-01

    A revised set of rules is in use at Gentilly-2 NGS for the selection of channels for refuelling. Traditional hard channel rejection rules (of go/no-go type) have been replaced by a more efficient set of soft evaluation rules based on concepts borrowed to the Fuzzy Logic. New evaluation rules, labelled as 'Floppy Rules', enable to assess and rate the channel suitability for refuelling by using a smooth and natural continuum of values qualifying excellent, good, fair and poor choices. Global channel suitability for refuelling is measured by combining separate ratings obtained from individual evaluation rules. Each evaluation rule is based on a specific control parameter related to local or lumped core properties. Two new software codes (NEWRULES and REFUEL) designed around the concept of Floppy Rules enable to perform a very efficient selection of optimized channel refuelling sequences either in manual and automatic mode. (author)

  13. Low-Cost Methane Liquefaction Plant and Vehicle Refueling Station

    International Nuclear Information System (INIS)

    Wilding, B.; Bramwell, D.

    1999-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is currently negotiating a collaborative effort with Pacific Gas and Electric (PG and E) that will advance the use of liquefied natural gas (LNG) as a vehicle fuel. We plan to develop and demonstrate a small-scale methane liquefaction plant (production of 5,000 to 10,000 gallons per day) and a low-cost ($150,000) LNG refueling station to supply fuel to LNG-powered transit buses and other heavy-duty vehicles. INEEL will perform the research and development work. PG and E will deploy the new facilities commercially in two demonstration projects, one in northern California, and one in southern California

  14. Design study for KALIMER upper internal structure and reactor refueling system

    International Nuclear Information System (INIS)

    Park, Jin Ho

    1996-09-01

    The design study for the KALIMER upper internal structure (UIS) and reactor refueling system has been described. Two distinct features are plug-in UIS and extended refueling outage. For the UIS system, the functional, structural and material requirements have been determined and the accommodation approaches to meet these functional requirements described. For the refueling system, the functional, structural, process and I and C (Instrument and Control) requirements have been established and the accommodation approaches for the functional and process requirements described. The impact on plant availability due to extension of the refueling outage has also been investigated. The accommodation approaches for UIS system show that the design concept of the system will satisfy the functional requirements with a few design issues to be resolved, such as UIS plug in/out handling system and cask design. It is also shown that the functional and process requirements of the refueling system are achievable with the design of the IVTM cask and related transfer system and the extended refueling outage has little effect (within 1%) on the plant availability if extra refueling time do not exceed 1 week. 1 refs. (Author)

  15. A Distance-Adaptive Refueling Recommendation Algorithm for Self-Driving Travel

    Directory of Open Access Journals (Sweden)

    Quanli Xu

    2018-03-01

    Full Text Available Taking the maximum vehicle driving distance, the distances from gas stations, the route length, and the number of refueling gas stations as the decision conditions, recommendation rules and an early refueling service warning mechanism for gas stations along a self-driving travel route were constructed by using the algorithm presented in this research, based on the spatial clustering characteristics of gas stations and the urgency of refueling. Meanwhile, by combining ArcEngine and Matlab capabilities, a scenario simulation system of refueling for self-driving travel was developed by using c#.net in order to validate and test the accuracy and applicability of the algorithm. A total of nine testing schemes with four simulation scenarios were designed and executed using this algorithm, and all of the simulation results were consistent with expectations. The refueling recommendation algorithm proposed in this study can automatically adapt to changes in the route length of self-driving travel, the maximum driving distance of the vehicle, and the distance from gas stations, which could provide variable refueling recommendation strategies according to differing gas station layouts along the route. Therefore, the results of this study could provide a scientific reference for the reasonable planning and timely supply of vehicle refueling during self-driving travel.

  16. Design study for KALIMER upper internal structure and reactor refueling system

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Ho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-09-01

    The design study for the KALIMER upper internal structure (UIS) and reactor refueling system has been described. Two distinct features are plug-in UIS and extended refueling outage. For the UIS system, the functional, structural and material requirements have been determined and the accommodation approaches to meet these functional requirements described. For the refueling system, the functional, structural, process and I and C (Instrument and Control) requirements have been established and the accommodation approaches for the functional and process requirements described. The impact on plant availability due to extension of the refueling outage has also been investigated. The accommodation approaches for UIS system show that the design concept of the system will satisfy the functional requirements with a few design issues to be resolved, such as UIS plug in/out handling system and cask design. It is also shown that the functional and process requirements of the refueling system are achievable with the design of the IVTM cask and related transfer system and the extended refueling outage has little effect (within 1%) on the plant availability if extra refueling time do not exceed 1 week. 1 refs. (Author).

  17. Safety approach to the selection of design criteria for the CRBRP reactor refueling system

    International Nuclear Information System (INIS)

    Meisl, C.J.; Berg, G.E.; Sharkey, N.F.

    1979-01-01

    The selection of safety design criteria for Liquid Metal Fast Breeder Reactor (LMFBR) refueling systems required the extrapolation of regulations and guidelines intended for Light Water Reactor refueling systems and was encumbered by the lack of benefit from a commercially licensed predecessor other than Fermi. The overall approach and underlying logic are described for developing safety design criteria for the reactor refueling system (RRS) of the Clinch River Breeder Reactor Plant (CRBRP). The complete selection process used to establish the criteria is presented, from the definition of safety functions to the finalization of safety design criteria in the appropriate documents. The process steps are illustrated by examples

  18. Fuel management study on quarter core refueling for Ling Ao NPP

    International Nuclear Information System (INIS)

    Zhang Hong; Li Jinggang

    2012-01-01

    The fuel management study on quarter core refueling is introduced for Ling Ao NPP. Starting from the selection of the objective of fuel management for quarter core refueling, the code and method used and the analysis carried out are explained in details to reach the final loading pattern chosen. The start-up physics test results are listed to demonstrate the realized quarter core fuel management. In the end, the advantage and disadvantage after turning to quarter core refueling has been given for the power plant from the fuel management point of view. (authors)

  19. Current status of the development of the refuelable aluminum-air battery

    Science.gov (United States)

    Cooper, J. F.; Kraftick, K. A.; McKinley, B. J.

    1983-05-01

    The technical status of a refuelable aluminum air battery using flowing caustic aluminate electrolyte at 50 to 700 C is reviewed. Four distinct designs for rapidly refuelable cells were evaluated in single or multicell modules on an engineering scale (167 to 1000 cm(2)/cell). Consideration is given to cells of the wedge configuration, which allow partial recharge, high anode utilization, and rapid refueling. Kinetic models developed for aluminum trihydroxide precipitation are used to predict the behavior of integrated cell/crystallizer systems. Drive cycle life and polarization data are reviewed for air electrodes under simulated vehicle operating conditions. Problems in the development of cost effective anode alloys are described. These results are interpreted from the perspective of the potential of an aluminum air battery to provide an electric vehicle with the range, acceleration and rapid refueling capabilities of common automobiles.

  20. Improvement in or relating to methods and apparatus for refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Shumyakin, E.P.; Sabir-de-Ribas, K.I.; Druzhinsky, I.A.; Kondratiev, P.V.; Andreichikov, B.I.; Slepov, L.M.; Borisjuk, E.V.; Smirnov, A.M.

    1977-01-01

    This invention relates to improvements in the methods and in the apparatus used for refuelling liquid metal cooled fast reactors and in particular to systems for cooling the fuel assemblies as they are removed from the reactor. (UK)

  1. Relative position control design of receiver UAV in flying-boom aerial refueling phase.

    Science.gov (United States)

    An, Shuai; Yuan, Suozhong

    2018-02-01

    This paper proposes the design of the relative position-keeping control of the receiver unmanned aerial vehicle (UAV) with the time-varying mass in the refueling phase utilizing an inner-outer loop structure. Firstly, the model of the receiver in the refueling phase is established. And then tank model is set up to analyze the influence of fuel transfer on the receiver. Subsequently, double power reaching law based sliding mode controller is designed to control receiver translational motion relative to tanker aircraft in the outer loop while active disturbance rejection control technique is applied to the inner loop to stabilize the receiver. In addition, the closed-loop stabilities of the subsystems are established, respectively. Finally, an aerial refueling model under various refueling strategies is utilized. Simulations and comparative analysis demonstrate the effectiveness and robustness of the proposed controllers. Copyright © 2017 ISA. Published by Elsevier Ltd. All rights reserved.

  2. Refueling Infrastructure for Alternative Fuel Vehicles: Lessons Learned for Hydrogen; Workshop Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Melaina, M. W.; McQueen, S.; Brinch, J.

    2008-07-01

    DOE sponsored the Refueling Infrastructure for Alternative Fuel Vehicles: Lessons Learned for Hydrogen workshop to understand how lessons from past experiences can inform future efforts to commercialize hydrogen vehicles. This report contains the proceedings from the workshop.

  3. Air Force Air Refueling: The KC-X Aircraft Acquisition Program

    National Research Council Canada - National Science Library

    Knight, William; Bolkcom, Christopher

    2008-01-01

    ... to accomplish air refueling missions. The program is expected to cost approximately $35 billion. Both Boeing and a consortium consisting of Northrop Grumman and European Aeronautic Defence and Space Company...

  4. Exposure to regular gasoline and ethanol oxyfuel during refueling in Alaska.

    OpenAIRE

    Backer, L C; Egeland, G M; Ashley, D L; Lawryk, N J; Weisel, C P; White, M C; Bundy, T; Shortt, E; Middaugh, J P

    1997-01-01

    Although most people are thought to receive their highest acute exposures to gasoline while refueling, relatively little is actually known about personal, nonoccupational exposures to gasoline during refueling activities. This study was designed to measure exposures associated with the use of an oxygenated fuel under cold conditions in Fairbanks, Alaska. We compared concentrations of gasoline components in the blood and in the personal breathing zone (PBZ) of people who pumped regular unleade...

  5. Refueling emissions from cars in Japan: Compositions, temperature dependence and effect of vapor liquefied collection system

    Science.gov (United States)

    Yamada, Hiroyuki; Inomata, Satoshi; Tanimoto, Hiroshi

    2015-11-01

    Refueling emissions from cars available on the Japanese market, which were not equipped with specific controlling devices, were investigated. For the composition analysis, a proton transfer reaction plus switchable reagent ion mass spectrometry (PTR + SRI-MS), which is capable of real-time measurement, was used. In addition, the performance of a vapor liquefied collection system (VLCS), which is a recently developed controlling device, was evaluated and compared with an onboard refueling vapor recovery (ORVR) system. The refueling emission factor of uncontrolled vehicles at 20 °C was 1.02 ± 0.40 g/L in the case dispensing 20 L of fuel. The results of composition analysis indicated that the maximum incremental reactivity (MIR) of refueling emissions in Japan was 3.49 ± 0.83. The emissions consist of 80% alkanes and 20% alkenes, and aromatics and di-enes were negligible. C4 alkene had the highest impact on the MIR of refueling emissions. The amounts of refueling emissions were well reproduced by a function developed by MOVE2010 in the temperature range of 5-35 °C. The compositions of the refueling emissions varied in this temperature range, but the change in MIR was negligible. The trapping efficiency of VLCS was the same level as that of the ORVR (over 95%). The MIRs of refueling and evaporative emissions were strongly affected by that of the test fuel. This study and our previous study indicated that MIRbreakthrough ≈ MIRrefueling ≈ MIRfuel + 0.5 and MIRpermeation ≈ MIRfuel. The real-world estimated average MIRfuel in Japan was about 3.0.

  6. Advanced CANDU reactors fuel analysis through optimal fuel management at approach to refuelling equilibrium

    International Nuclear Information System (INIS)

    Tingle, C.P.; Bonin, H.W.

    1999-01-01

    The analysis of alternate CANDU fuels along with natural uranium-based fuel was carried out from the view point of optimal in-core fuel management at approach to refuelling equilibrium. The alternate fuels considered in the present work include thorium containing oxide mixtures (MOX), plutonium-based MOX, and Pressurised Water Reactor (PWR) spent fuel recycled in CANDU reactors (Direct Use of spent PWR fuel in CANDU (DUPIC)); these are compared with the usual natural UO 2 fuel. The focus of the study is on the 'Approach to Refuelling Equilibrium' period which immediately follows the initial commissioning of the reactor. The in-core fuel management problem for this period is treated as an optimization problem in which the objective function is the refuelling frequency to be minimized by adjusting the following decision variables: the channel to be refuelled next, the time of the refuelling and the number of fresh fuel bundles to be inserted in the channel. Several constraints are also included in the optimisation problem which is solved using Perturbation Theory. Both the present 37-rod CANDU fuel bundle and the proposed CANFLEX bundle designs are part of this study. The results include the time to reach refuelling equilibrium from initial start-up of the reactor, the average discharge burnup, the average refuelling frequency and the average channel and bundle powers relative to natural UO 2 . The model was initially tested and the average discharge burnup for natural UO 2 came within 2% of the industry accepted 199 MWh/kgHE. For this type of fuel, the optimization exercise predicted the savings of 43 bundles per full power year. In addition to producing average discharge burnups and other parameters for the advanced fuels investigated, the optimisation model also evidenced some problem areas like high power densities for fuels such as the DUPIC. Perturbation Theory has proven itself to be an accurate and valuable optimization tool in predicting the time between

  7. A repeatedly refuelable mediated biofuel cell based on a hierarchical porous carbon electrode

    Science.gov (United States)

    Fujita, Shuji; Yamanoi, Shun; Murata, Kenichi; Mita, Hiroki; Samukawa, Tsunetoshi; Nakagawa, Takaaki; Sakai, Hideki; Tokita, Yuichi

    2014-05-01

    Biofuel cells that generate electricity from renewable fuels, such as carbohydrates, must be reusable through repeated refuelling, should these devices be used in consumer electronics. We demonstrate the stable generation of electricity from a glucose-powered mediated biofuel cell through multiple refuelling cycles. This refuelability is achieved by immobilizing nicotinamide adenine dinucleotide (NAD), an electron-transfer mediator, and redox enzymes in high concentrations on porous carbon particles constituting an anode while maintaining their electrochemical and enzymatic activities after the immobilization. This bioanode can be refuelled continuously for more than 60 cycles at 1.5 mA cm-2 without significant potential drop. Cells assembled with these bioanodes and bilirubin-oxidase-based biocathodes can be repeatedly used to power a portable music player at 1 mW cm-3 through 10 refuelling cycles. This study suggests that the refuelability within consumer electronics should facilitate the development of long and repeated use of the mediated biofuel cells as well as of NAD-based biosensors, bioreactors, and clinical applications.

  8. A Comparative Study on the Refueling Simulation Method for a CANDU Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Do, Quang Binh; Choi, Hang Bok; Roh, Gyu Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    The Canada deuterium uranium (CANDU) reactor calculation is typically performed by the RFSP code to obtain the power distribution upon a refueling. In order to assess the equilibrium behavior of the CANDU reactor, a few methods were suggested for a selection of the refueling channel. For example, an automatic refueling channel selection method (AUTOREFUEL) and a deterministic method (GENOVA) were developed, which were based on a reactor's operation experience and the generalized perturbation theory, respectively. Both programs were designed to keep the zone controller unit (ZCU) water level within a reasonable range during a continuous refueling simulation. However, a global optimization of the refueling simulation, that includes constraints on the discharge burn-up, maximum channel power (MCP), maximum bundle power (MBP), channel power peaking factor (CPPF) and the ZCU water level, was not achieved. In this study, an evolutionary algorithm, which is indeed a hybrid method based on the genetic algorithm, the elitism strategy and the heuristic rules for a multi-cycle and multi-objective optimization of the refueling simulation has been developed for the CANDU reactor. This paper presents the optimization model of the genetic algorithm and compares the results with those obtained by other simulation methods.

  9. Laser driven pellet refuelling for JET (and reactor) uses

    International Nuclear Information System (INIS)

    Spalding, I.J.

    1978-11-01

    Published estimates of pellet sizes and velocities required to refuel JET and post-JET experiments are summarized. Possible advantages and difficulties of accelerating solid, unconstrained hydrogenic (and also jacketed) pellets to these velocities using laser techniques are then discussed. An essential problem to be solved is adequate axial guidance of the pellet during its acceleration, since laser pulse durations of many sound-transit times (in the solid D 2 ) are necessary to avoid shock-heating the pellet. It is shown that Culham's multikilojoule CO 2 TROJAN laser facility is well suited to testing many of the concepts proposed. In particular it is shown that successful verification, and subsequent optimization, of such (novel) techniques would permit single shot tests of contemporary pellet ablation theories by the injection of approximately 1 mm diameter D 2 pellets at velocities 6 cm s -1 into the JET plasma. Means for scaling these techniques to repetition rates of order 10 Hz, and to the 1 cm pellet diameters possibly required in a working Tokamak reactor, are also discussed. (author)

  10. Refueling the RPI reactor facility with low-enrichment fuel

    International Nuclear Information System (INIS)

    Harris, D.R.; Rodriguez-Vera, F.; Wicks, F.E.

    1985-01-01

    The RPI Critical Facility has operated since 1963 with a core of thin, highly enriched fuel plates in twenty-five fuel assembly boxes. A program is underway to refuel the reactor with 4.81 w/o enriched SPERT (F-1) fuel rods. Use of these fuel rods will upgrade the capabilities of the reactor and will eliminate a security risk. Adequate quantities of SPERT (F-1) fuel rods are available, and their use will result in a great cost saving relative to manufacturing new low-enrichment fuel plates. The SPERT fuel rods are 19 inches longer than are the present fuel plates, so a modified core support structure is required. It is planned to support and position the SPERT fuel pins by upper and lower lattice plates, thus avoiding the considerable cost of new fuel assembly boxes. The lattice plates will be secured to the existing top and bottom plates. The design permits the fabrication and use of other lattice plates for critical experiment research programs in support of long-lived full development for power reactors. (author)

  11. A simplified burnup calculation strategy with refueling in static molten salt reactor

    International Nuclear Information System (INIS)

    Srivastava, A.K.; Gupta, Anurag; Krishnani, P.D.

    2015-01-01

    Molten Salt Reactors, by nature can be refuelled and reprocessed online. Thus, a simulation methodology has to be developed which can consider online refueling and reprocessing aspect of the reactor. To cater such needs a simplified burnup calculation strategy to account for refueling and removal of molten salt fuel at any desired burnup has been identified in static molten salt reactor in batch mode as a first step of way forward. The features of in-house code ITRAN has been explored for such calculations. The code also enables us to estimate the reactivity introduced in the system due to removal of any number of considered nuclides at any burnup. The effect of refueling fresh fuel and removal of burned fuel has been studied in batch mode with in-house code ITRAN. The effect of refueling and burnup on change in reactivity per day has been analyzed. The analysis of removal of 233 Pa at a particular burnup has been carried out. The similar analysis has been performed for some other nuclides also. (author)

  12. Anti-disturbance rapid vibration suppression of the flexible aerial refueling hose

    Science.gov (United States)

    Su, Zikang; Wang, Honglun; Li, Na

    2018-05-01

    As an extremely dangerous phenomenon in autonomous aerial refueling (AAR), the flexible refueling hose vibration caused by the receiver aircraft's excessive closure speed should be suppressed once it appears. This paper proposed a permanent magnet synchronous motor (PMSM) based refueling hose servo take-up system for the vibration suppression of the flexible refueling hose. A rapid back-stepping based anti-disturbance nonsingular fast terminal sliding mode (NFTSM) control scheme with a specially established finite-time convergence NFTSM observer is proposed for the PMSM based hose servo take-up system under uncertainties and disturbances. The unmeasured load torque and other disturbances in the PMSM system are reconstituted by the NFTSM observer and to be compensated during the controller design. Then, with the back-stepping technique, a rapid anti-disturbance NFTSM controller is proposed for the PMSM angular tracking to improve the tracking error convergence speed and tracking precision. The proposed vibration suppression scheme is then applied to PMSM based hose servo take-up system for the refueling hose vibration suppression in AAR. Simulation results show the proposed scheme can suppress the hose vibration rapidly and accurately even the system is exposed to strong uncertainties and probe position disturbances, it is more competitive in tracking accuracy, tracking error convergence speed and robustness.

  13. Extension of the time-average model to Candu refueling schemes involving reshuffling

    International Nuclear Information System (INIS)

    Rouben, Benjamin; Nichita, Eleodor

    2008-01-01

    Candu reactors consist of a horizontal non-pressurized heavy-water-filled vessel penetrated axially by fuel channels, each containing twelve 50-cm-long fuel bundles cooled by pressurized heavy water. Candu reactors are refueled on-line and, as a consequence, the core flux and power distributions change continuously. For design purposes, a 'time-average' model was developed in the 1970's to calculate the average over time of the flux and power distribution and to study the effects of different refueling schemes. The original time-average model only allows treatment of simple push-through refueling schemes whereby fresh fuel is inserted at one end of the channel and irradiated fuel is removed from the other end. With the advent of advanced fuel cycles and new Candu designs, novel refueling schemes may be considered, such as reshuffling discharged fuel from some channels into other channels, to achieve better overall discharge burnup. Such reshuffling schemes cannot be handled by the original time-average model. This paper presents an extension of the time-average model to allow for the treatment of refueling schemes with reshuffling. Equations for the extended model are presented, together with sample results for a simple demonstration case. (authors)

  14. The development of AI-based refueling control system to the FUGEN NPP

    International Nuclear Information System (INIS)

    Nanko, Takashi; Tanaka, Koichi.

    1996-01-01

    Since even skilled workers spent a considerable time to perform the refueling work previously, an automatic control system was developed by using φNET, an AI tool and its application to refueling works was started in practice. In this system, the optimum plan for the refueling work was constructed using a network which allows to present the equipments to handle the fuel, as well as the operational roles obtained from the worker's experiences. Based on the plan, the instruments concerned were automatically operated to collect the data on the actual operation, the expression and/or printing was made on the movement histories of the articles and the status of their storages. By the development of the system, optimization of refueling works, rationalization of the management and the improvement of reliability for the works became possible. The development was performed in the following two steps; the first was development of an off-line system providing an operational guidance ot the operator according to the optimum operation plan and the second was development of an on-line system which allows to automatically control the instruments according to the operational plan. The off-line system has been put into practice since 1991 and the automatic operation of refueling has been started with the on-line system from 1995. (M.N.)

  15. Experiences with the upgraded SKP system during refuelling Paks nuclear power plant

    International Nuclear Information System (INIS)

    Baranyai, A.; Hetzmann, A.

    1997-01-01

    In order to control the neutron flux during the refueling period, new measuring chains were developed and put into operation by the experts of KFKI-RegTron Co., Ltd. and the Paks Nuclear Power Plant with the purpose of partially substituting the original Refuelling Neutron Monitoring system (SKP) of WWER-440 reactor units. The modified monitoring system processes the signals of detectors located in channels outside the core. The outputs of measurement amplifiers equipped with up-to-date electronics fit in the original system perfectly. Use of the out-of-core measuring technique confirmed the preliminary expectations: interference sensitivity has decreased, the neutron/gamma ration increased and refueling time has become shorter by one to one-and-a-half day. The paper details the reasons for upgrading, the essence of utilized solutions and the operational experience. (author)

  16. Integrated services as the key to the optimisation of refueling outages

    International Nuclear Information System (INIS)

    Ortega, Juan; Gonzalez, Roberto; Gutierrez, Jose E.

    2010-01-01

    Refueling outages at nuclear power plants are subject to demanding improvement criteria in each and every one of the activities scheduled. The management of activities on the refueling floor, including the phases of opening and closing of the reactor vessel and associated tasks relating to the reactor internals, the unloading, loading and management of the irradiated fuel and activities requested for the in-service inspection of essential primary circuit components, are interventions that have an impact on the refueling critical path and whose overall integration allows for significant optimization of the entire management of this fundamental refueling activity. For several years now, ENUSA, as the company specializing in irradiated fuel services, TECNATOM as the company responsible for the in-service inspection of critical primary side components and Westinghouse as the technology provider and specialist in the supply of plant support services, have together formed a solid working team offering this integrated refueling service to the Spanish plants. Today, the new and heightened demands regarding the training and specialization of the personnel participating in refueling outages, the need to consider contingencies in the activities scheduled and the objectives relating to the ALARA concept and safe operations require that this service include new activities providing synergies and leading to higher levels of commitment to excellence. This paper will present the service model developed, the most significant activities integrated in the service and the advantages and milestones achieved and reached during this period, compared to the conventional distributed functions model. Likewise, an analysis will be made of the new challenges that are being addressed, with a view to bringing about a more global integration. (authors)

  17. Pellets for fusion reactor refueling. Annual progress report, January 1, 1976--December 31, 1976

    International Nuclear Information System (INIS)

    Turnbull, R.J.; Kim, K.

    1977-01-01

    The purpose of this research is to test the feasibility of refueling fusion reactors using solid pellets composed of fuel elements. A solid hydrogen pellet generator has been constructed and experiments have been done to inject the pellets into the ORMAK Tokamak. A theory has been developed to describe the pellet ablation in the plasma, and an excellent agreement has been found between the theory and the experiment. Techniques for charging the pellets have been developed in order to accelerate and control them. Other works currently under way include the development of techniques for accelerating the pellets for refueling purpose. Evaluation of electrostatic acceleration has also been performed

  18. Computer simulation for risk management: Hydrogen refueling stations and water supply of a large region

    DEFF Research Database (Denmark)

    Markert, Frank; Kozine, Igor

    2012-01-01

    in applying DES models to the analysis of large infrastructures for refueling stations and water supply. Two case studies are described which are concerned with the inherently safer supply and storage of hydrogen at refueling stations and an established drinking water supply system of a large metropolitan...... area, respectively. For both, the simulation aims at identifying points of potential improvement from the reliability point of view. This allows setting up a list of activities and safety measures to reduce risk and possible losses and mitigate the consequences of accidents. Based on the cases...

  19. [CFD numerical simulation onto the gas-liquid two-phase flow behavior during vehicle refueling process].

    Science.gov (United States)

    Chen, Jia-Qing; Zhang, Nan; Wang, Jin-Hui; Zhu, Ling; Shang, Chao

    2011-12-01

    With the gradual improvement of environmental regulations, more and more attentions are attracted to the vapor emissions during the process of vehicle refueling. Research onto the vehicle refueling process by means of numerical simulation has been executed abroad since 1990s, while as it has never been involved so far domestically. Through reasonable simplification about the physical system of "Nozzle + filler pipe + gasoline storage tank + vent pipe" for vehicle refueling, and by means of volume of fluid (VOF) model for gas-liquid two-phase flow and Re-Normalization Group kappa-epsilon turbulence flow model provided in commercial computational fluid dynamics (CFD) software Fluent, this paper determined the proper mesh discretization scheme and applied the proper boundary conditions based on the Gambit software, then established the reasonable numerical simulation model for the gas-liquid two-phase flow during the refueling process. Through discussing the influence of refueling velocity on the static pressure of vent space in gasoline tank, the back-flowing phenomenon has been revealed in this paper. It has been demonstrated that, the more the flow rate and the refueling velocity of refueling nozzle is, the higher the gross static pressure in the vent space of gasoline tank. In the meanwhile, the variation of static pressure in the vent space of gasoline tank can be categorized into three obvious stages. When the refueling flow rate becomes higher, the back-flowing phenomenon of liquid gasoline can sometimes be induced in the head section of filler pipe, thus making the gasoline nozzle pre-shut-off. Totally speaking, the theoretical work accomplished in this paper laid some solid foundation for self-researching and self-developing the technology and apparatus for the vehicle refueling and refueling emissions control domestically.

  20. Analysis on engineering application of CNP1000 in-containment refueling water storage tank

    International Nuclear Information System (INIS)

    Wang Bin; Wang Yong; Qiu Jian; Weng Minghui

    2005-01-01

    Based on the basic design of CNP1000 (three loops), which is self-reliance designed by China National Nuclear Cooperation, and investigation results from abroad advanced nuclear power plant design of In-containment Refueling Water Storage tank, this paper describe the system flowsheet, functional requirements, structural design and piping arrangement about In-containment Refueling Water Storage Tank. The design takes the lower structural space as the IRWST. Four areas are configured to meet the diverse functional requirements, including depressurization area, water collection area, safety injection and/or containment spray suction area, TSP storage area / reactor cavity flooding holdup tank. Also the paper depict the corresponding analysis and demonstration, such as In-containment Refueling Water Storage Tank pressure transient on depressurization area of IRWST, suction and internal flow stream of IRWST, configuration of strains, the addition method and amount of chemical addition, design and engineering applicant of Reactor Cavity Flooding System. All the analysis results show the basic design of IRWST meeting with the Utility Requirement Document's requirements on performance of safety function, setting of overfill passage, overpressure protection, related interference, etc., and show the reliability of Engineering Safety Features being improved for CNP1000 (three loops). Meanwhile, it is demonstrated that the design of In-containment Refueling Water Storage Tank can apply on the future nuclear power plant project in China. (authors)

  1. Strength analysis of refueling machine for large PWR in nuclear power plant

    International Nuclear Information System (INIS)

    Jia Xiaofeng; Zhou Guofeng; Bi Xiangjun; Ji Shunying

    2010-01-01

    The refueling machine of PWR plays important roles in nuclear power plant operation,and the dynamic analysis and strength assessment should be carried out to check its safety. In this paper, the finite element model (FEM) was established with the software ANSYS 12 for the refueling machine structure of large 1 000 MW PWR. The dynamic computations were performed under three work conditions, i.e. normal (cart starting and braking), abnormal (OBE) and accident(SSE) conditions, respectively. The structure responses (internal force and stress) of refueling machine under earthquake response spectrum in three directions were combined with the method of square root of square sum (SRSS). Moreover, the static response under gravity was also considered to construct the most critical conditions. With the simulated results, the strength of main structure, bold and weld joint,and the stability of landing leg for additional crane were assessed based on the RCCM code. At last, the local stress analysis of finger-form hook, which function is to take fuel assemblies, was also analyzed, while its strength was also assessed. The results show that the strengths of the refueling machine under various working conditions can meet the safety requirements. (authors)

  2. 14 CFR 29.979 - Pressure refueling and fueling provisions below fuel level.

    Science.gov (United States)

    2010-01-01

    ..., DEPARTMENT OF TRANSPORTATION AIRCRAFT AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY ROTORCRAFT Powerplant Fuel System § 29.979 Pressure refueling and fueling provisions below fuel level. (a) Each fueling connection... from that tank in case of malfunction of the fuel entry valve. (b) For systems intended for pressure...

  3. Support services to refuelling exploitation; Servicios de apoyo a explotacion en recarga

    Energy Technology Data Exchange (ETDEWEB)

    Castineira, M; Cortes, M.; Rayo, A.

    2010-07-01

    The refuelling period in nuclear power stations is very important due to the need to optimise its duration, large volumes of work and resources that have to be planned and coordinated and their impact on the subsequent operating cycle. Empresarios Agrupados has a permanent organisation, with specialised resources and extensive availability of human resources. (Author)

  4. Pellets for fusion reactor refueling. Annual progress report, 1 January 1975--31 December 1975

    International Nuclear Information System (INIS)

    Turnbull, R.J.

    1976-01-01

    The feasibility of refueling fusion reactors using pellets of deuterium-tritium is discussed. A pellet injector has been constructed and experiments have been done injecting solid pellets into the ORMAK machine. Theoretical explanations of the results from these experiments have been successful. Other experiments underway include techniques for charging the pellets in order to accelerate and control them

  5. Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995

    International Nuclear Information System (INIS)

    Mendoza L, A.; Flores C, E.; Lopez G, C.P.F.

    1995-01-01

    The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author)

  6. Design Status and Applications of Small reactors without On-site Refuelling

    International Nuclear Information System (INIS)

    Kuznetsov, V.

    2006-01-01

    Small reactors without on-site refuelling are the reactors that can operate without reloading and shuffling of fuel for a reasonably long period, consistent with plant economy and considerations of energy security, with no fresh or spent fuel being stored at a site during reactor operation. Such reactors could simplify the implementation of safeguards and provide certain guarantees of sovereignty to those countries that would prefer to lease fuel from a foreign vendor or, perhaps, an international fuel cycle centre. About 30 concepts of such reactors are being analyzed or developed in 6 IAEA Member States. They cover all principle reactor lines: water cooled, fast gas cooled, sodium cooled, lead or lead bismuth cooled and molten salt cooled reactors. An increased refuelling interval could be achieved with reduced core power density, burnable absorbers, or high conversion ratio. The design goals for small reactors without on-site refuelling, inter alia, include: difficult unauthorized access to fuel; design provisions to facilitate the implementation of safeguards; capability to survive all postulated accident scenarios without requiring emergency response in the public domain; economic competitiveness for anticipated market conditions and applications; the capability to achieve higher manufacturing quality through factory mass production, design standardization and common basis for design certification; and a flexibility in siting and applications. Such reactors are often considered in conjunction with fuel or NPP leasing Small reactors without on-site refuelling have many common technology development issues related to the provision of lifetime core operation, economic competitiveness, high level of safety and proliferation resistance. Reestablishment of a practice of licensing by test and establishment of legal provisions and the insurance scheme for a transit of fuel loads or factory fabricated reactors through the territory of a third country are mentioned as

  7. The influence of the placement method of fuel dispenserson the refueling cycle of vehicles

    Directory of Open Access Journals (Sweden)

    Levin Ruslan Yur’evich

    2015-05-01

    Full Text Available Logistics of production processes at a gas station is a critical point in the system of petroleum products, on the operation of which the effectiveness and sustainability of the transport sector depends. The provision and supply of road transportation of petroleum products is one of the most urgent tasks.Technological processes of reception, storage of fuel and refuelling of motor vehicles on petrol stations needs a scientific study of their structure and organization. At the design stage of a gas station, it is necessary to consider quite a lot of different factors: the configuration of the area under the gas station, the scheme of arrangement and the number of fuel dispensers, the trajectory of motion and the design of vehicles, calls to the station, distance between cars on duty, between the elements of buildings and equipment, as well as the requirements for fire, building, public, sanitary-epidemiological and state regulations. Therefore, the designer has a great opportunity for varying the parameters of the elements of the station, especially when considering the characteristics of the fueled vehicles.Typical projects at a same power station include various sizes, the seizure of land to build a station changes from planning decisions and the locations of all its technological elements. For increase of functioning efficiency of transportation systems of petroleum products in modern conditions on the basis of the design and technical innovations it is necessary to conduct special studies.Research planning decisions for a refueling station led to the conclusion that the placement of technological equipment in the refueling area has a certain impact on the length of vehicles service. Improving the layout of the refueling zone several times reduces the loss of the components of the refueling cycle time and increase the capacity of the station.Information base describing the stages of a gas station includes parts of refueling cycle time and

  8. Automated procedure for selection of optimal refueling policies for light water reactors

    International Nuclear Information System (INIS)

    Lin, B.I.; Zolotar, B.; Weisman, J.

    1979-01-01

    An automated procedure determining a minimum cost refueling policy has been developed for light water reactors. The procedure is an extension of the equilibrium core approach previously devised for pressurized water reactors (PWRs). Use of 1 1/2-group theory has improved the accuracy of the nuclear model and eliminated tedious fitting of albedos. A simple heuristic algorithm for locating a good starting policy has materially reduced PWR computing time. Inclusion of void effects and use of the Haling principle for axial flux calculations extended the nuclear model to boiling water reactors (BWRs). A good initial estimate of the refueling policy is obtained by recognizing that a nearly uniform distribution of reactivity provides low-power peaking. The initial estimate is improved upon by interchanging groups of four assemblies and is subsequently refined by interchanging individual assemblies. The method yields very favorable results, is simpler than previously proposed BWR fuel optimization schemes, and retains power cost as the objective function

  9. Interim qualitative risk assessment for an LNG refueling station and review of relevant safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Siu, N.; Herring, S.; Cadwallader, L.; Reece, W.; Byers, J.

    1997-07-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tanker truck delivers and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects analysis and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of best practice information throughout the LNG community.

  10. Qualitative Risk Assessment for an LNG Refueling Station and Review of Relevant Safety Issues

    Energy Technology Data Exchange (ETDEWEB)

    Siu, N.; Herring, J.S.; Cadwallader, L.; Reece, W.; Byers, J.

    1998-02-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural gas (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tank truck deliveries, and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects Analysis, and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of ``best practice`` information throughout the LNG community.

  11. Refueling Stop Activity Detection and Gas Station Extraction Using Crowdsourcing Vehicle Trajectory Data

    Directory of Open Access Journals (Sweden)

    YANG Wei

    2017-07-01

    Full Text Available In view of the deficiencies of current surveying methods of gas station, an approach is proposed to extract gas station from vehicle traces. Firstly, the spatial-temporal characteristics of individual and collective refueling behavior of trajectory is analyzed from aspects of movement features and geometric patterns. Secondly, based on Stop/Move model, the velocity sequence linear clustering algorithm is proposed to extract refueling stop tracks. Finally, using the methods including Delaunay triangulation, Fourier shape recognition and semantic constraints to identify and extract gas station. An experiment using 7 days taxi GPS traces in Beijing verified the novel method. The experimental results of 482 gas stations are extracted and the correct rate achieves to 93.1%.

  12. Management of individual and collective dosimetry at Fessenheim nuclear plant. Evaluation after refueling shutdown

    International Nuclear Information System (INIS)

    Lamarre, D.; Waller, A.

    1980-01-01

    The principle of dosimetry management chosen by Fessenheim nuclear power station was originally consisted of two phases: - an automatic acquisition of individual doses realized by stylodosimeter readers; - a deferred data processing by computer. The whole system has not been used during the shutdown for the first refuelling of unit number one in view of encountered difficulties with perfecting of automatic readers prototype, this last phase has been replaced by a manual acquisition of doses. The dosimetry data processing has two main objects: - supervision of individual dosimetry for people who work in the nuclear power station; - knowledge of doses assigned for each working and equipment. Moreover, a first dosimetric result of the shutdown for refuelling of unit number one, enables to notice the workings which doses are the most important and written in percentage of total doses: regulatory controls: about 19%; - steam generators working: 16%; - working decontamination and making health physics screen (lock chamber) 10% [fr

  13. REFUEL. The harvest so far. Papers to the 15th European Biomass Conference and Exhibition, May 2007

    International Nuclear Information System (INIS)

    2007-01-01

    The REFUEL project is designed to encourage a greater market penetration of biofuels. To help achieve this goal, we will develop a biofuels road map, consistent with EU biofuel policies and supported by stakeholders involved in the biofuels field. Starting early 2006, the project involves seven renowned partners and will take 24 months to complete. Refuel is financed by the European Commission under the 'Intelligent Energy - Europe' programme. This report contains papers that were presented at the title conference

  14. Environmental and biological monitoring of benzene during self-service automobile refueling.

    OpenAIRE

    Egeghy, P P; Tornero-Velez, R; Rappaport, S M

    2000-01-01

    Although automobile refueling represents the major source of benzene exposure among the nonsmoking public, few data are available regarding such exposures and the associated uptake of benzene. We repeatedly measured benzene exposure and uptake (via benzene in exhaled breath) among 39 self-service customers using self-administered monitoring, a technique rarely used to obtain measurements from the general public (130 sets of measurements were obtained). Benzene exposures averaged 2.9 mg/m(3) (...

  15. Optimal mission planning of GEO on-orbit refueling in mixed strategy

    Science.gov (United States)

    Chen, Xiao-qian; Yu, Jing

    2017-04-01

    The mission planning of GEO on-orbit refueling (OOR) in Mixed strategy is studied in this paper. Specifically, one SSc will be launched to an orbital slot near the depot when multiple GEO satellites are reaching their end of lives. The SSc replenishes fuel from the depot and then extends the lifespan of the target satellites via refueling. In the mixed scenario, only some of the target satellites could be served by the SSc, and the remaining ones will be fueled by Pseudo SScs (the target satellite which has already been refueled by the SSc and now has sufficient fuel for its operation as well as the fuel to refuel other target satellites is called Pseudo SSc here). The mission sequences and fuel mass of the SSc and Pseudo SScs, the dry mass of the SSc are used as design variables, whereas the economic benefit of the whole mission is used as design objective. The economic cost and benefit models are stated first, and then a mathematical optimization model is proposed. A comprehensive solution method involving enumeration, particle swarm optimization and modification is developed. Numerical examples are carried out to demonstrate the effectiveness of the model and solution method. Economic efficiencies of different OOR strategies are compared and discussed. The mixed strategy would perform better than the other strategies only when the target satellites satisfy some conditions. This paper presents an available mixed strategy scheme for users and analyzes its advantages and disadvantages by comparing with some other OOR strategies, providing helpful references to decision makers. The best strategy in practical applications depends on the specific demands and user preference.

  16. Unmanned Carrier-Based Aircraft System: Debate over Systems Role Led to Focus on Aerial Refueling

    Science.gov (United States)

    2016-03-24

    Unmanned Carrier-Based Aircraft System: Debate over System’s Role Led to Focus on Aerial Refueling Prior to February 2016, the Navy had planned to...Background In a May 2015 report, we found that the intended mission and required capabilities of UCLASS were under review as there was debate ...environments, or largely strike with limited surveillance capability operating in highly contested environments.2 This debate delayed the expected

  17. Management of refuelling, modifications and accidental shut-down of nuclear power plant

    International Nuclear Information System (INIS)

    1996-01-01

    This document is the appendix of HAF 0300 (91) 'Code on the Safety of Nuclear Power Plant Operation', which was promulgated by the National Nuclear Safety Administration (NNSA) on March 2, 1994, and has the same legal effect. This appendix is applicable to establish the administrative management procedures for refuelling, modifications and accidental shut-down in the period of operation of pressurized water thermal neutron reactor of nuclear power plants. The NNSA shall be responsible for interpretation of this document

  18. Investigating attitudes to hydrogen refuelling facilities and the social cost to local residents

    International Nuclear Information System (INIS)

    O'Garra, Tanya; Mourato, Susana; Pearson, Peter

    2008-01-01

    Vehicles fuelled by hydrogen (H 2 ) have attracted increasing attention because of their potentially enhanced environmental profiles. Their penetration into the vehicle stock will be influenced by the spread of refuelling facilities. This study investigates local attitudes towards the proposed installation of H 2 storage facilities at existing refuelling stations throughout London. Using multinomial logit analysis, we identify the determinants of attitudes. Results suggest that residents living very close to a proposed H 2 facility are less likely to be opposed than residents living 200-500 m away. Opposition appears to be determined by a lack of trust in safety regulations, non-environmental attitudes, and concerns about the existing local refuelling station. The social cost to local residents of a local H 2 storage facility was estimated using a method developed by Atkinson et al. [2004. 'Amenity' or 'eyesore'? Negative willingness to pay for options to replace electricity transmission towers. Applied Economics Letters 11(4), 203-208], which elicits the amount of time respondents are willing to commit to oppose a new facility development. Using the leisure rate of time, the social cost is estimated at just under Pounds 14 per local opposed resident. Add to this the WTP to support opposition efforts by a local group, and the value comes to just under Pounds 25 per opposed resident

  19. Refueling Behavior of Flexible Fuel Vehicle Drivers in the Federal Fleet

    Energy Technology Data Exchange (ETDEWEB)

    Daley, R.; Nangle, J.; Boeckman, G.; Miller, M.

    2014-05-01

    Federal fleets are a frequent subject of legislative and executive efforts to lead a national transition to alternative fuels and advanced vehicle technologies. Section 701 of the Energy Policy Act of 2005 requires that all dual-fueled alternative fuel vehicles in the federal fleet be operated on alternative fuel 100% of the time when they have access to it. However, in Fiscal Year (FY) 2012, drivers of federal flex fuel vehicles (FFV) leased through the General Services Administration refueled with E85 24% of the time when it was available--falling well short of the mandate. The U.S. Department of Energy's National Renewable Energy Laboratory completed a 2-year Laboratory Directed Research and Development project to identify the factors that influence the refueling behavior of federal FFV drivers. The project began with two primary hypotheses. First, information scarcity increases the tendency to miss opportunities to purchase E85. Second, even with perfect information, there are limits to how far drivers will go out of their way to purchase E85. This paper discusses the results of the project, which included a June 2012 survey of federal fleet drivers and an empirical analysis of actual refueling behavior from FY 2009 to 2012. This research will aid in the design and implementation of intervention programs aimed at increasing alternative fuel use and reducing petroleum consumption.

  20. Natural circulation analysis for the advanced neutron source reactor refueling process 11

    Energy Technology Data Exchange (ETDEWEB)

    Tucker, R.F.; Dasardhi, S.; Elkassabgi, Y. [Texas A& M Univ., Kingsville, TX (United States); Yoder, G.L. [Oak Ridge National Lab., TN (United States)

    1995-09-01

    During the refueling process of the Advanced Neutron Source Reactor (ANSR), the spent fuel elements must be moved from the primary coolant loop (containing D{sub 2}O), through a heavy water pool, and finally into a light water spent fuel storage area. The present refueling scheme utilizes remote refueling equipment to move the spent fuel elements through a D{sub 2}O filled stack and tunnel into a temporary storage canal. A transfer lock is used to move the spent fuel elements from the D{sub 2}O-filled interim storage canal to a light water pool. Each spent fuel element must be cooled during this process, using either natural circulation or forced convection. This paper presents a summary of the numerical techniques used to analyze natural circulation cooling of the ANSR fuel elements as well as selected results of the calculations. Details of the analysis indicate that coolant velocities below 10 cm/s exist in the coolant channels under single phase natural circulation conditions. Also, boiling does not occur within the channels if power levels are below a few hundred kW when the core transitions to natural circulation conditions.

  1. The achievement of on-load refuelling at Heysham 2 and Torness AGRs

    International Nuclear Information System (INIS)

    Sterland, P.R.; MacPherson, D.

    1995-01-01

    Heysham 2 and Torness are the last of the advanced gas cooled reactors constructed for the Central Electricity Generating Board and the South of Scotland Electricity Board. They are now operated by Nuclear Electric (NE) and Scottish Nuclear Limited (SNL), respectively. They were designed for on-load refuelling at high power and, being based on the design used for Hinkley Point B and Hunterston B, have benefited from experience at these stations. This paper examines the analysis work which was carried out in order to provide a sound, long-term, mainly probabilistic safety case which supports on-load refuelling. A significant problem has been that the design reliability of the microprocessor-based control and protection systems, used for the fuel route, could not be justified, and a number of changes to the overall protection system have had to be introduced to compensate for this. The safety assessment has covered the fuelling machine pressure boundary, the hoist and fuel assembly components, possible faults and the protection which is necessary to prevent them, the fuel and fuelling machine cooling requirements, the mechanical and radiological consequences of dropping fuel, and the effect of refuelling transients on the reactor and conventional plant. The resultant safety case complies with the stringent safety standards adopted by NE and SNL and accepted by the UK safety authority, the Nuclear Installations Inspectorate (NII). (author)

  2. Refueling availability for alternative fuel vehicle markets: Sufficient urban station coverage

    International Nuclear Information System (INIS)

    Melaina, Marc; Bremson, Joel

    2008-01-01

    Alternative fuel vehicles can play an important role in addressing the challenges of climate change, energy security, urban air pollution and the continued growth in demand for transportation services. The successful commercialization of alternative fuels for vehicles is contingent upon a number of factors, including vehicle cost and performance. Among fuel infrastructure issues, adequate refueling availability is one of the most fundamental to successful commercialization. A commonly cited source reports 164,300 refueling stations in operation nationwide. However, from the perspective of refueling availability, this nationwide count tends to overstate the number of stations required to support the widespread deployment of alternative fuel vehicles. In terms of spatial distribution, the existing gasoline station networks in many urban areas are more than sufficient. We characterize a sufficient level of urban coverage based upon a subset of cities served by relatively low-density station networks, and estimate that some 51,000 urban stations would be required to provide this sufficient level of coverage to all major urban areas, 33 percent less than our estimate of total urban stations. This improved characterization will be useful for engineering, economic and policy analyses. (author)

  3. Towards a standardized grasping and refuelling on-orbit servicing for geo spacecraft

    Science.gov (United States)

    Medina, Alberto; Tomassini, Angelo; Suatoni, Matteo; Avilés, Marcos; Solway, Nick; Coxhill, Ian; Paraskevas, Iosif S.; Rekleitis, Georgios; Papadopoulos, Evangelos; Krenn, Rainer; Brito, André; Sabbatinelli, Beatrice; Wollenhaupt, Birk; Vidal, Christian; Aziz, Sarmad; Visentin, Gianfranco

    2017-05-01

    Exploitation of space must benefit from the latest advances in robotics. On-orbit servicing is a clear candidate for the application of autonomous rendezvous and docking mechanisms. However, during the last three decades most of the trials took place combining extravehicular activities (EVAs) with telemanipulated robotic arms. The European Space Agency (ESA) considers that grasping and refuelling are promising near-mid-term capabilities that could be performed by servicing spacecraft. Minimal add-ons on spacecraft to enhance their serviceability may protect them for a changing future in which satellite servicing may become mainstream. ESA aims to conceive and promote standard refuelling provisions that can be installed in present and future European commercial geostationary orbit (GEO) satellite platforms and scientific spacecraft. For this purpose ESA has started the ASSIST activity addressing the analysis, design and validation of internal provisions (such as modifications to fuel, gas, electrical and data architecture to allow servicing) and external provisions (such as integrated berthing fixtures with peripheral electrical, gas, liquid connectors, leak check systems and corresponding optical and radio markers for cooperative rendezvous and docking). This refuelling approach is being agreed with European industry (OHB, Thales Alenia Space) and expected to be consolidated with European commercial operators as a first step to become an international standard; this approach is also being considered for on-orbit servicing spacecraft, such as the SpaceTug, by Airbus DS. This paper describes in detail the operational means, structure, geometry and accommodation of the system. Internal and external provisions will be designed with the minimum possible impact on the current architecture of GEO satellites without introducing additional risks in the development and commissioning of the satellite. End-effector and berthing fixtures are being designed in the range of few

  4. Development of a dose database in the refuelling scenario of a nuclear power plant for a virtual reality application

    International Nuclear Information System (INIS)

    Rodenas, J.; Zarza, I.; Pascual, A.; Felipe, A.; Sanchez-Mayoral, M.L.

    2002-01-01

    Operators in Nuclear Power Plants can receive high doses during refuelling operation. A training program simulating refuelling operations will be useful to reduce doses received by workers as well as to minimise operation time. With this goal in mind a Virtual Reality application is developed in the frame of CIPRES Project (Calculos Interactivos de Proteccion Radiologica en un Entorno de Simulacion - Interactive Calculations of Radiological Protection in a Simulation Environment), a RD project sponsored by IBERINCO and developed jointly by IBERINCO and the Nuclear Engineering Department of the Polytechnic University of Valencia. The Virtual Reality application requires the possibility of displaying doses, both instantaneous and accumulated, at all times during the operator training. Therefore, it is necessary to elaborate a database containing dose rates at every point of the refuelling plant. This database is elaborated from Radiological Protection Surveillance data measured throughout the plant during refuelling operation. To estimate doses throughout the refuelling plant some interpolation routines have been used. Different assumptions have been adopted in order to perform the interpolation and obtain consistent data. In this paper, procedures developed to elaborate the dose database for the Virtual Reality application are presented and analysed

  5. Automatic refueling platform and CRD remote handling device for BWR plant

    International Nuclear Information System (INIS)

    Kato, Hiroaki; Takagi, Kaoru

    1978-01-01

    In BWR plants, machines for replacing fuel assemblies and control rod drives are usually operated directly by personnel. An automatic refueling platform and a CRD remote handling device aiming at radiation exposure reduction and handling perfectness are described, which are already used in BWR plants. Automation of the former is achieved in transporting fuel assemblies between a reactor pressure vessel and a fuel storage pool, shuffling fuel assemblies in a reactor core and moving fuel assemblies in a fuel storage pool. In the latter, replacement of CRDs is nearly all performed remotely. (Mori, K.)

  6. Extending the features of RBMK refuelling machine simulator with a training tool based on virtual reality

    International Nuclear Information System (INIS)

    Khoudiakov, M.; Slonimsky, V.; Mitrofanov, S.

    2004-01-01

    The paper describes a continuation of efforts of an international Russian - Norwegian joint team to improve operational safety during the refuelling process of an RBMK-type reactor by implementing a training simulator based on an innovative Virtual Reality (VR) approach. During the preceding 1st stage of the project a display-based simulator was extended with VR models of the real Refuelling Machine (RM) and its environment in order to improve both the learning process and operation's effectiveness. The simulator's challenge is to support the performance (operational activity) of RM operational staff firstly by helping them to develop basic knowledge and skills as well as to keep skilled staff in close touch with the complex machinery of the Refuelling Machine. During the 2nd stage of the joint project the functional scope of the VR-simulator was greatly enhanced - firstly, by connecting to the RBMK-unit full-scope simulator, and, secondly, by including a training program and simulator model upgrade. The present 3rd stage of the Project is primarily oriented towards the improvement of the training process for maintenance and operational personnel by means of a development of the Training Support Methodology and Courses (TSMC) to be based on Virtual Reality and enlarged functionality of 3D and process modelling. The TMSC development is based on Russian and International Regulatory Bodies requirements and recommendations. Design, development and creation of a specialised VR-based Training System for RM Maintenance Personnel are very important for the Russian RBMK plants. The main goal is to create a powerful, autonomous VR-based simulator for training technical maintenance personnel on the Refuelling Machine. VR based training is expected to improve the effect of training compared to the current training based on traditional methods using printed documentation. The LNPP management and the Regulatory Bodies supported this goal. The VR-based Training System should

  7. The development of calculational methods and assessment standards for AGR refuelling safety cases

    International Nuclear Information System (INIS)

    Dawson, J.W.; Grant, R.J.; Thomas, D.L.

    1995-01-01

    This paper considers the methods used to assess the protection needed against hazards in the AGR fuel route. These methods are all directed towards the objective of showing that all postulated events taking place during refuelling are acceptable within agreed criteria of severity versus frequency. The methods allow the determination of temperatures arising in various hazards, from which estimates can be made of the radiological release, if any, which would occur. Comparison of this estimate with the level considered acceptable at the fault frequency leads to the requirement for protection. (author)

  8. Integrated head area design of KNGR to reduce refueling outage duration

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo Tae; Park, Chi Yong; Kim, In Hwan; Kim, Dae Woong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    In the design of KNGR (Korea Next Generation Reactor), we believe that economy is one of the most important factors to be considered. Thus, we reviewed and evaluated the consequences of designing the head area into an integrated package from an economical point of view. The refueling outage durations of the nuclear power plants currently in operation in Korea, some having and others not having integrated head package, are compared. This paper discusses the characteristics of head area design and the critical design issues of KNGR head area to evaluate the effect of the head area characteristics on the outage duration. 8 refs., 4 figs. (Author)

  9. Integrated head area design of KNGR to reduce refueling outage duration

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo Tae; Park, Chi Yong; Kim, In Hwan; Kim, Dae Woong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    In the design of KNGR (Korea Next Generation Reactor), we believe that economy is one of the most important factors to be considered. Thus, we reviewed and evaluated the consequences of designing the head area into an integrated package from an economical point of view. The refueling outage durations of the nuclear power plants currently in operation in Korea, some having and others not having integrated head package, are compared. This paper discusses the characteristics of head area design and the critical design issues of KNGR head area to evaluate the effect of the head area characteristics on the outage duration. 8 refs., 4 figs. (Author)

  10. Study of Some Innovant Reactors without on- Site Refueling with Triso and Cermet Fuel

    OpenAIRE

    A.Chetaine; A. Benchrif; H. Amsil; V. Kuznetsov; Y. Shimazu

    2012-01-01

    The evaluation of unit cell neutronic parameters and lifetime for some innovant reactors without on sit-refuling will be held in this work. the behavior of some small and medium reactors without on site refueling with triso and cermet fuel. For the FBNR long life except we propose to change the enrichment of the Cermet MFE to 9%. For the AFPR reactor we can see that the use of the Cermet MFE can extend the life of this reactor but to maintain the same life period for AFPR...

  11. The design and use of proficiency based BWR reactor maintenance and refuelling training mockups

    International Nuclear Information System (INIS)

    Ford, G.J.

    1996-01-01

    The purpose of this paper is to describe the ABB experience with the design and use of boiling water reactor training facilities. The training programs were developed and implemented in cooperation with the nuclear utilities. ABB operates two facilities, the ABB ATOM Light Water Reactor Service Center located in Vasteras, Sweden, and the ABB Combustion Engineering Nuclear Operations BWR Training Center located in Chattanooga, Tennessee, USA. The focus of the training centers are reactor maintenance and refueling activities plus the capability to develop and qualify tools, procedures and repair techniques

  12. Community Energy: Analysis of Hydrogen Distributed Energy Systems with Photovoltaics for Load Leveling and Vehicle Refueling

    Energy Technology Data Exchange (ETDEWEB)

    Steward, D.; Zuboy, J.

    2014-10-01

    Energy storage could complement PV electricity generation at the community level. Because PV generation is intermittent, strategies must be implemented to integrate it into the electricity system. Hydrogen and fuel cell technologies offer possible PV integration strategies, including the community-level approaches analyzed in this report: (1) using hydrogen production, storage, and reconversion to electricity to level PV generation and grid loads (reconversion scenario); (2) using hydrogen production and storage to capture peak PV generation and refuel hydrogen fuel cell electric vehicles (FCEVs) (hydrogen fueling scenario); and (3) a comparison scenario using a battery system to store electricity for EV nighttime charging (electric charging scenario).

  13. Drogue tracking using 3D flash lidar for autonomous aerial refueling

    Science.gov (United States)

    Chen, Chao-I.; Stettner, Roger

    2011-06-01

    Autonomous aerial refueling (AAR) is an important capability for an unmanned aerial vehicle (UAV) to increase its flying range and endurance without increasing its size. This paper presents a novel tracking method that utilizes both 2D intensity and 3D point-cloud data acquired with a 3D Flash LIDAR sensor to establish relative position and orientation between the receiver vehicle and drogue during an aerial refueling process. Unlike classic, vision-based sensors, a 3D Flash LIDAR sensor can provide 3D point-cloud data in real time without motion blur, in the day or night, and is capable of imaging through fog and clouds. The proposed method segments out the drogue through 2D analysis and estimates the center of the drogue from 3D point-cloud data for flight trajectory determination. A level-set front propagation routine is first employed to identify the target of interest and establish its silhouette information. Sufficient domain knowledge, such as the size of the drogue and the expected operable distance, is integrated into our approach to quickly eliminate unlikely target candidates. A statistical analysis along with a random sample consensus (RANSAC) is performed on the target to reduce noise and estimate the center of the drogue after all 3D points on the drogue are identified. The estimated center and drogue silhouette serve as the seed points to efficiently locate the target in the next frame.

  14. Considering the dynamic refueling behavior in locating electric vehicle charging stations

    Science.gov (United States)

    Liu, K.; Sun, X. H.

    2014-11-01

    Electric vehicles (EVs) will certainly play an important role in addressing the energy and environmental challenges at current situation. However, location problem of EV charging stations was realized as one of the key issues of EVs launching strategy. While for the case of locating EV charging stations, more influence factors and constraints need to be considered since the EVs have some special attributes. The minimum requested charging time for EVs is usually more than 30minutes, therefore the possible delay time due to waiting or looking for an available station is one of the most important influence factors. In addition, the intention to purchase and use of EVs that also affects the location of EV charging stations is distributed unevenly among regions and should be considered when modelling. Unfortunately, these kinds of time-spatial constraints were always ignored in previous models. Based on the related research of refuelling behaviours and refuelling demands, this paper developed a new concept with dual objectives of minimum waiting time and maximum service accessibility for locating EV charging stations - named as Time-Spatial Location Model (TSLM). The proposed model and the traditional flow-capturing location model are applied on an example network respectively and the results are compared. Results demonstrate that time constraint has great effects on the location of EV charging stations. The proposed model has some obvious advantages and will help energy providers to make a viable plan for the network of EV charging stations.

  15. REFUEL. Potential and realizable cost reduction of 2nd generation biofuels

    International Nuclear Information System (INIS)

    Londo, H.M.; Deurwaarder, E.P.; Lensink, S.M.; Junginer, H.M.; De Wit, M.

    2007-05-01

    In the REFUEL project steering possibilities for and impacts of a greater market penetration of biofuels are assessed. Several benefits are attributed to second generation biofuels, fuels made from lignocellulosic feedstock, such as higher productivity, less impacts on land use and food markets and improved greenhouse gas emission reductions. The chances of second generation biofuels entering the market autonomously are assessed and several policy measures enhancing those changes are evaluated. It shows that most second generation biofuels might become competitive in the biofuel market, if the production of biodiesel from oil crops becomes limited by land availability. Setting high biofuel targets, setting greenhouse gas emissions caps on biofuel and setting subtargets for second generation biofuels, all have a similar impact of stimulating second generation's entrance into the biofuel market. Contrary, low biofuel targets and high imports can have a discouraging impact on second generation biofuel development, and thereby on overall greenhouse gas performance. Since this paper shows preliminary results from the REFUEL study, one is advised to contact the authors before quantitatively referring to this paper

  16. The achievement of on-load refuelling at Heysham 2 and Torness AGRs

    International Nuclear Information System (INIS)

    Sterland, P.R.; MacPherson, D.

    1995-01-01

    Heysham 2 and Torness are the last of the advanced gas cooled reactors (AGR) constructed for the Central Electricity Generating Board and the South of Scotland Electricity Board. They are now operated by Nuclear Electric (NE) and Scottish Nuclear Limited (SNL) respectively. They were designed for on load refuelling at high power and being based on the design used for Hinkley Point B and Hunterston B, have benefited from experience at these stations. This paper examines the analysis work which was carried out in order to provide a sound, long term, mainly probabilistic safety case which supports on load refuelling. A significant problem has been that the design reliability of the microprocessor based control and protection systems, used for the fuel route, could not be justified and a number of changes to the overall protection system have had to be introduced to compensate for this. The resultant safety case complies with the stringent safety standards adopted by NE and SNL and accepted by the UK safety authority, the Nuclear Installations Inspectorate (NII). (author)

  17. Use of an advanced document system in post-refuelling updating of nuclear power plant documentation

    International Nuclear Information System (INIS)

    Puech Suanzes, P.; Cortes Soler, M.

    1993-01-01

    This paper discusses the results of the extensive use of an advanced document system to update documentation prepared by traditional methods and affected by changes in the period between two plant refuellings. The implementation of a system for the capture, retrieval and storage of drawings using optical discs is part of a plan to modernize production and management tools and to thus achieve better control of document configuration. These processes are consequently optimized in that: 1. The deterioration of drawings is detained with the help of an identical, updated, legible, reliable support for all users. 2. The time required to update documentation is reduced. Given the large number of drawings, the implementation method should effectively combine costs and time. The document management tools ensure optical disc storage control so that from the moment a drawing resides in the system, any modification to it is made through the system utilities, thus ensuring quality and reducing schedules. The system described was used to update the electrical drawings of Almaraz Nuclear Power Plant. Changes made during the eighth refuelling of Unit I were incorporated and the time needed to issue the updated drawings was reduced by one month. (author)

  18. Optimization of refueling-shuffling scheme in PWR core by random search strategy

    International Nuclear Information System (INIS)

    Wu Yuan

    1991-11-01

    A random method for simulating optimization of refueling management in a pressurized water reactor (PWR) core is described. The main purpose of the optimization was to select the 'best' refueling arrangement scheme which would produce maximum economic benefits under certain imposed conditions. To fulfill this goal, an effective optimization strategy, two-stage random search method was developed. First, the search was made in a manner similar to the stratified sampling technique. A local optimum can be reached by comparison of the successive results. Then the other random experiences would be carried on between different strata to try to find the global optimum. In general, it can be used as a practical tool for conventional fuel management scheme. However, it can also be used in studies on optimization of Low-Leakage fuel management. Some calculations were done for a typical PWR core on a CYBER-180/830 computer. The results show that the method proposed can obtain satisfactory approach at reasonable low computational cost

  19. WLAN Hot Spot services for the automotive and oil industries :a business analysis Or : "Refuel the car with petrol and information, both ways at the gas station"

    NARCIS (Netherlands)

    L-F. Pau (Louis-François); M.H.P. Oremus

    2003-01-01

    textabstractWhile you refuel for gas ,why not refuel for information or download vehicle data ? This paper analyzes in extensive detail the user segmentation by vehicle usage , service offering , and full business models from WLAN hot spot services delivered to vehicles (private, professional ,

  20. Developing a virtual reality application for training Nuclear Power Plant operators: Setting up a database containing dose rates in the refuelling plant

    International Nuclear Information System (INIS)

    Rodenas, J.; Zarza, I.; Burgos, M. C.; Felipe, A.; Sanchez-Mayoral, M. L.

    2004-01-01

    Operators in Nuclear Power Plants can receive high doses during refuelling operations. A training programme for simulating refuelling operations will be useful in reducing the doses received by workers as well as minimising operation time. With this goal in mind, a virtual reality application is developed within the framework of the CIPRES project. The application requires doses, both instantaneous and accumulated, to be displayed at all times during operator training. Therefore, it is necessary to set up a database containing dose rates at every point in the refuelling plant. This database is based on radiological protection surveillance data measured in the plant during refuelling operations. Some interpolation routines have been used to estimate doses through the refuelling plant. Different assumptions have been adopted in order to perform the interpolation and obtain consistent data. In this paper, the procedures developed to set up the dose database for the virtual reality application are presented and analysed. (authors)

  1. Status and Prospects of the Global Automotive Fuel Cell Industry and Plans for Deployment of Fuel Cell Vehicles and Hydrogen Refueling Infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    Greene, David L [ORNL; Duleep, Gopal [HD Systems

    2013-06-01

    Automobile manufacturers leading the development of mass-market fuel cell vehicles (FCVs) were interviewed in Japan, Korea, Germany and the United States. There is general agreement that the performance of FCVs with respect to durability, cold start, packaging, acceleration, refueling time and range has progressed to the point where vehicles that could be brought to market in 2015 will satisfy customer expectations. However, cost and the lack of refueling infrastructure remain significant barriers. Costs have been dramatically reduced over the past decade, yet are still about twice what appears to be needed for sustainable market success. While all four countries have plans for the early deployment of hydrogen refueling infrastructure, the roles of government, industry and the public in creating a viable hydrogen refueling infrastructure remain unresolved. The existence of an adequate refueling infrastructure and supporting government policies are likely to be the critical factors that determine when and where hydrogen FCVs are brought to market.

  2. GPS navigation algorithms for Autonomous Airborne Refueling of Unmanned Air Vehicles

    Science.gov (United States)

    Khanafseh, Samer Mahmoud

    Unmanned Air Vehicles (UAVs) have recently generated great interest because of their potential to perform hazardous missions without risking loss of life. If autonomous airborne refueling is possible for UAVs, mission range and endurance will be greatly enhanced. However, concerns about UAV-tanker proximity, dynamic mobility and safety demand that the relative navigation system meets stringent requirements on accuracy, integrity, and continuity. In response, this research focuses on developing high-performance GPS-based navigation architectures for Autonomous Airborne Refueling (AAR) of UAVs. The AAR mission is unique because of the potentially severe sky blockage introduced by the tanker. To address this issue, a high-fidelity dynamic sky blockage model was developed and experimentally validated. In addition, robust carrier phase differential GPS navigation algorithms were derived, including a new method for high-integrity reacquisition of carrier cycle ambiguities for recently-blocked satellites. In order to evaluate navigation performance, world-wide global availability and sensitivity covariance analyses were conducted. The new navigation algorithms were shown to be sufficient for turn-free scenarios, but improvement in performance was necessary to meet the difficult requirements for a general refueling mission with banked turns. Therefore, several innovative methods were pursued to enhance navigation performance. First, a new theoretical approach was developed to quantify the position-domain integrity risk in cycle ambiguity resolution problems. A mechanism to implement this method with partially-fixed cycle ambiguity vectors was derived, and it was used to define tight upper bounds on AAR navigation integrity risk. A second method, where a new algorithm for optimal fusion of measurements from multiple antennas was developed, was used to improve satellite coverage in poor visibility environments such as in AAR. Finally, methods for using data-link extracted

  3. Investigation of in-cabin volatile organic compounds (VOCs) in taxis; influence of vehicle's age, model, fuel, and refueling.

    Science.gov (United States)

    Bakhtiari, Reza; Hadei, Mostafa; Hopke, Philip K; Shahsavani, Abbas; Rastkari, Noushin; Kermani, Majid; Yarahmadi, Maryam; Ghaderpoori, Afshin

    2018-06-01

    The air pollutant species and concentrations in taxis' cabins can present significant health impacts on health. This study measured the concentrations of benzene, toluene, ethylbenzene, xylene (BTEX), formaldehyde, and acetaldehyde in the cabins of four different taxi models. The effects of taxi's age, fuel type, and refueling were investigated. Four taxi models in 3 age groups were fueled with 3 different fuels (gas, compressed natural gas (CNG), and liquefied petroleum gas (LPG)), and the concentrations of 6 air pollutants were measured in the taxi cabins before and after refueling. BTEX, formaldehyde, and acetaldehyde sampling were actively sampled using NIOSH methods 1501, 2541, and 2538, respectively. The average BTEX concentrations for all taxi models were below guideline values. The average concentrations (±SD) of formaldehyde in Model 1 to Model 4 taxis were 889 (±356), 806 (±323), 1144 (±240), and 934 (±167) ppbv, respectively. Acetaldehyde average concentrations (±SD) in Model 1 to Model 4 taxis were 410 (±223), 441 (±241), 443 (±210), and 482 (±91) ppbv, respectively. Refueling increased the in-vehicle concentrations of pollutants primarily the CNG and LPG fuels. BTEX concentrations in all taxi models were significantly higher for gasoline. Taxi age inversely affected formaldehyde and acetaldehyde. In conclusion, it seems that refueling process and substitution of gasoline with CNG and LPG can be considered as solutions to improve in-vehicle air concentrations for taxis. Copyright © 2018. Published by Elsevier Ltd.

  4. Design for air-to-air refuelling operations; new passenger and tanker aircraft design for AAR scenarios

    NARCIS (Netherlands)

    Li, M.O.

    2014-01-01

    Air-to-air refuelling is a way to improve fuel efficiency of the overall transport system without waiting for the improvement of basic aviation technology. To take full advantage of such an operation, both passenger aircraft and tanker aircraft (which deliver required fuel to the passenger aircraft

  5. Research and Development of a PEM Fuel Cell, Hydrogen Reformer, and Vehicle Refueling Facility

    Energy Technology Data Exchange (ETDEWEB)

    Edward F. Kiczek

    2007-08-31

    Air Products and Chemicals, Inc. has teamed with Plug Power, Inc. of Latham, NY, and the City of Las Vegas, NV, to develop, design, procure, install and operate an on-site hydrogen generation system, an alternative vehicle refueling system, and a stationary hydrogen fuel cell power plant, located in Las Vegas. The facility will become the benchmark for validating new natural gas-based hydrogen systems, PEM fuel cell power generation systems, and numerous new technologies for the safe and reliable delivery of hydrogen as a fuel to vehicles. Most important, this facility will serve as a demonstration of hydrogen as a safe and clean energy alternative. Las Vegas provides an excellent real-world performance and durability testing environment.

  6. Feasibility study on application of WIMS-AECL to Wolsong-1 refueling simulation

    International Nuclear Information System (INIS)

    Kim, Y.; Lee, S.

    2005-01-01

    'Full text:' At present, in Wolsong nuclear power plant, all of the reactor physics calculations are based on the cell code POWDERPUFS-V (PPV). PPV code use semi-empirical approximation rather than direct solving of transport equation with robust methodology. Switch from PPV to more robust transport solver is world-wide trend in addition to GAI issued from Canadian regulatory body (CNSC). In this paper, feasibility study on the replacement of cell code POWDERPUFS-V (PPV) with WIMS-AECL was performed for Wolsong-1 NPP. The impact of the cell code replacement on physics design parameters and refueling simulation was assessed. First, fuel isotopic composition affecting core reactivity is compared between PPV and WIMS-AECL. Generally it was shown that WIMS-AECL predicts higher uranium fissile concentration while less plutonium concentration as fuel burnup increases compared with prediction of PPV. Infinite multiplication factor of WIMS-AECL is slightly less predicted than that of PPV. Also core reactivity change from operating condition change such as moderator temperature, coolant temperature, fuel temperature and coolant density were compared for both fresh fuel and equilibrium fuel. Specially the analysis of void reactivity which is current hot issue for positive reactivity insertion in LOCA was also performed. As a result of this study, all of WIMS-AECL results were similar to PPV based calculation in the fresh fuel. However, there is a tendency that the deviation between the two codes increases as the fuel burn-up increases. This is because PPV code was made from the laboratory condition with fresh fuel and low fuel temperature. Second, refueling simulation with WIMS-AECL based RFSP was tried to compare with current PPV based RFSP simulation for about 20 months (5775FPD ∼ 6324FPD). To cover wide range of operating parameter condition such as purity of moderator and coolant and boron concentration, tremendous amount of computation time is needed with WIMS

  7. Detection and Tracking Strategies for Autonomous Aerial Refuelling Tasks Based on Monocular Vision

    Directory of Open Access Journals (Sweden)

    Yingjie Yin

    2014-07-01

    Full Text Available Detection and tracking strategies based on monocular vision are proposed for autonomous aerial refuelling tasks. The drogue attached to the fuel tanker aircraft has two important features. The grey values of the drogue's inner part are different from the external umbrella ribs, as shown in the image. The shape of the drogue's inner dark part is nearly circular. According to crucial prior knowledge, the rough and fine positioning algorithms are designed to detect the drogue. Particle filter based on the drogue's shape is proposed to track the drogue. A strategy to switch between detection and tracking is proposed to improve the robustness of the algorithms. The inner dark part of the drogue is segmented precisely in the detecting and tracking process and the segmented circular part can be used to measure its spatial position. The experimental results show that the proposed method has good performance in real-time and satisfied robustness and positioning accuracy.

  8. Hydrogen for buses in London: A scenario analysis of changes over time in refuelling infrastructure costs

    International Nuclear Information System (INIS)

    Shayegan, S.; Pearson, P.J.G.; Hart, D.

    2009-01-01

    The lack of a hydrogen refuelling infrastructure is one of the major obstacles to the introduction of the hydrogen vehicles to the road transport market. To help overcome this hurdle a likely transitional solution is to introduce hydrogen for niche applications such as buses or other types of fleet vehicles for which fuel demand is predictable and localised. This paper analyses the costs of different hydrogen production-delivery pathways, via a case study of buses in London. Scenario analysis over time (2007-2025) is used to investigate potential changes to the cost of hydrogen as a result of technology development, growing demand for hydrogen and changes in energy prices (gas and electricity). It is found that factors related to hydrogen demand have the greatest effect on the unit cost of hydrogen, while for the whole of the analysis period, on-site SMR (steam methane reforming) remains the least-cost production-delivery pathway. (author)

  9. Operational transparency: an advanced safeguards strategy for future on-load refuelled reactors

    International Nuclear Information System (INIS)

    Whitlock, J.J.; Trask, D.

    2012-01-01

    The IAEA's system for tracking fuel movement in an on-load refuelled heavy-water reactor is robust, but an opportunity remains to exploit the wealth of data streaming from the reactor vault during operation and provide real-time, third-party monitoring of reactor status and history. This concept of Operational Transparency would require that large amounts of operational data be reduced in near-real time to a small subset of high-level information. Operational Transparency would enhance the IAEA's ability to monitor the state of the core to an unprecedented level. This paper provides an overview of the novel concept of Operational Transparency in heavy water reactors, using potential application to CANDU reactors as an example, and explores some of the technical challenges that will need to be solved for efficient implementation. (author)

  10. Device for refueling a nuclear reactor having a core comprising a plurality of fuel assemblies

    International Nuclear Information System (INIS)

    Van Santen, A.; Elofsson, K.

    1975-01-01

    A nuclear reactor formed of fuel assemblies each including a plurality of parallel fuel rods arranged in a predetermined fuel rod lattice, which rods are freely extractable and insertable at one end of the fuel assembly, is refueled by extracting from one of the fuel assemblies a number of fuel rods substantially less than the total number of fuel rods and replacing these by inserting new fuel rods into the vacated positions. The removal and return of the rods is produced by a tool having a plurality of gripping members capable of engaging shoulders beneath heads formed on the upper ends of the fuel rods. This may be accomplished by providing a tool having a number of gripping members attached to the tool body corresponding to the lattice positions of the fuel rods to be extracted, having gripping members which can be pushed together to grip beneath shoulders on the upper ends of the fuel rods. (Official Gazette)

  11. Validation of physics model of FARE-Tool by comparison of RFSP flux simulations with measurements at discrete refuelling steps

    International Nuclear Information System (INIS)

    Shad, M.A.

    1995-01-01

    In CANDU 6 the on-power refuelling is done in the direction of the coolant flow through the channel, flow being in alternate direction in adjacent channels. The channel flow pushes the fuel string (a total of 20 bundles with the 8-bundle fuelling scheme) towards the downstream Fuelling Machine (FM), obviating the need for the upstream FM to insert the rams into the active core to push the fuel. In some channels of the outer core region, however, the coolant flow is low and the hydraulic drag is not enough to push the fuel string. In these channels a Flow Assist Ram Extension (FARE) tool is used during refuelling to augment the flow and hence enhance the hydraulic drag required to push the fuel string. The FARE-Tool is a strong neutron absorber and its use results in a severe local flux depression. During the refuelling process, when the FARE-Tool travels in the immediate vicinity of a Reactor Regulating System (RRS) detector, the spatial control system causes a short-term zone-fill reduction in an attempt to maintain the reference zone powers. This short term zone drain may in turn result in a single channel ROP trip of the SDS l or SDS2 reactor protection system. Therefore, the control room operator is always interested in minimizing the occurrence of this category of trip for obvious economic reasons. The physics modelling of the FARE-Tool used in the 2-neutron-energy-group 3-dimensional diffusion code RFSP is validated by comparing the simulated response of the in-core detectors with the measured response of the same detectors during refuelling. These measurements were recorded during a specially scheduled refuelling of channel B09 at the Point Lepreau Generating Station on 1993 July 6 at 3591 Equivalent Full Power Days (EFPDs). 3 refs., 10 tabs., 1 fig

  12. General empirical model for 60Co generation in pressurized water reactors with continuous refueling

    International Nuclear Information System (INIS)

    Urrutia, G.A.; Blesa, M.A.; Fernandez-Prini, R.; Maroto, A.J.G.

    1984-01-01

    A simplified model is presented that permits one to calculate the average activity on the fuel elements of a reactor that operates under continuous refueling, based on the assumption of crud interchange between fuel element surface and coolant in the form of particulate material only and using the crud specific activity as an empirical parameter determined in plant. The net activity flux from core to out-of-core components is then calculated in the form of parametric curves depending on crud specific activity and rate of particulate release from fuel surface. In pressure vessel reactors, contribution to out-ofcore radionuclide inventory arising in the release of activated materials from core components must be taken into account. The contribution from in situ activation of core components is calculated from the rates of release and the specific activities corresponding to the exposed surface of the component (calculated in a straightforward way on the basis of core geometry and neutron fluxes). The rates of release can be taken from the literature, or in the case of cobalt-rich alloys, can be calculated from experimentally determined cobalt contents of structural components and crud. For pressure vessel reactors operating under continuous refueling, activation of deposited crud and release of activated materials are compared; the latter, in certain cases, may represent a sizable (and even the largest) fraction of the total cobalt activity. It is proposed that the ratio of activities of 59 Fe to 54 Mn may be used as a diagnostic tool for in situ activation of structural materials; available data indicate ratios close to unity for pressure tube heavy water reactors (no in situ activation) and ratios around 4 to 10 for pressure vessel, heavy water reactors

  13. Refueling and density control in the ZT-40M reversed field pinch

    International Nuclear Information System (INIS)

    Wurden, G.A.; Weber, P.G.; Watt, R.G.; Munson, C.P.; Cayton, T.E.; Buechl, K.

    1987-01-01

    The effects of pellet injection and gas puff refueling have been studied in the ZT-40M Reversed Field Pinch. Multiple deuterium pellets (≤ 6 x 10 19 D atoms/pellet) with velocities ranging from 300 to 700 m/sec have been injected into plasmas with n-bar/sub e/ ∼1 to 5 X 10 19 m -3 , I/sub phi/ ∼100 to 250 kA, T/sub e/(0) ∼150 to 300 eV and discharge durations of ≤ 20 msec. Photographs and an array D/sub α/ detectors show substantial deflection of the pellet trajectory in both the poloidal and toroidal planes, due to asymmetric ablation of the pellet by electrons streaming along field lines. To compensate for the poloidal deflection, the injector was moved up +14 cm off-axis, allowing the pellets to curve down to the midplane. In this fashion, central peaking of the pellet density deposition profile can be obtained. Both electron and ion temperatures fall in response to the density rise, such that β/sub θ/(β/sub θ/ identical to n-bar/sub e/(T/sub e/(0) + T/sub i/)/(B/sub θ/(a)) 2 ) remains roughly constant. Energy confinement is momentarily degraded, and typically a decrease in F (F identical to B/sub phi/(a)/(B/sub phi/)) is seen as magnetic energy is converted to plasma energy when the pellet ablates. As a result of pellet injection at I/sub phi/ = 150 kA we observe T/sub e/(0) α n-bar/sub e//sup -.9 +- .1/, while the helicity based resistivity eta/sub k/ transiently varies as n-bar/sub e//sup .7 +- .1/. While the achievement of center-peaked density profiles is possible with pellet injection, gas puffing at rates strong enough to show a 50% increase in n-bar/sub e/ over a period of 10 msec (∼150 torr-litres/sec) leads to hollow density profiles. The refueling requirements for parameters expected in the next generation RFPs (ZTH, RFX) can be extrapolated from these data using modified tokamak pellet ablation codes

  14. An analysis of fast reactor fuel assembly performance taking into account their mechanical interaction in the core and refuelling line capabilities

    International Nuclear Information System (INIS)

    Buksha, Yu.K.; Zabudko, L.M.; Kravchenko, I.N.; Matveenko, L.V.; Meshkov, M.N.

    1984-01-01

    An approach to assessment of fast reactor fuel assembly performance has been considered. A concept of passive restraint of fuel assemblies in a reactor adopted in the USSR is described. Some methods for calculating the interassembly interactions during operation are briefly outlined, some calculated results are presented. A problem of fuel assembly performance during refuelling taking into account the refuelling line capabilities is considered. Some results from fuel assemblies operation experience in the BN-600 reactor are given. (author)

  15. Application of railgun principle to high-velocity hydrogen pellet injection for magnetic fusion reactor refueling: Technical progress report

    International Nuclear Information System (INIS)

    Kim, Kyekyoon.

    1987-12-01

    This paper discusses the use of a railgun accelerator to inject hydrogen pellets into a magnetic fusion reactor for refueling purposes. Specific studies in this paper include: 1.5 mm-diameter two-stage fuseless plasma-arc-driven electromagnetic railgun, construction and testing of a 3.2 mm-diameter two-stage railgun and a theoretical analysis of the behavior of a railgun plasma-arc armature inside a railgun

  16. THE KINETICS OF CONTAMINANTS ACCUMULATION IN THE JET FUEL DURING THE TECHNOLOGICAL PROCESS OF ITS PREPARATION FOR AIRCRAFT REFUELING

    OpenAIRE

    A. A. Brailko

    2017-01-01

    Much attention is payed to the tasks for ensuring domestic and international aircraft safety and regularity, which are multifaceted and complex. One of them is the system of ensuring the quality of aviation fuel for refueling aircraft at airports. A significant influence of the quality, chemical composition and fuel range on the reliability and lifetime of components and parts of the aircraft fuel system was studied in the process of development and experience accumulation of aircraft operati...

  17. THE KINETICS OF CONTAMINANTS ACCUMULATION IN THE JET FUEL DURING THE TECHNOLOGICAL PROCESS OF ITS PREPARATION FOR AIRCRAFT REFUELING

    Directory of Open Access Journals (Sweden)

    A. A. Brailko

    2017-01-01

    Full Text Available Much attention is payed to the tasks for ensuring domestic and international aircraft safety and regularity, which are multifaceted and complex. One of them is the system of ensuring the quality of aviation fuel for refueling aircraft at airports. A significant influence of the quality, chemical composition and fuel range on the reliability and lifetime of components and parts of the aircraft fuel system was studied in the process of development and experience accumulation of aircraft operating, processes of aviation fuel production, as well as during storage, quality control, transportation, refueling preparation and aircraft refueling. Currently, work is being done to study the influence of fuel quality on the units of the technological scheme of fuel-filling complexes, which provide the required cleanliness of the fuel according to the regulations. The article describes the trend level of aviation fuel cleanliness at the stages from receipt to issuance to the refueling station. The evaluation of compliance with existing regulations on the level of jet fuel cleanliness and the efficiency of fuel cleaning facilities is carried out. It is stated that one of the problems of insufficient level of aviation fuel cleaning quality is a violation of the acceptable contamination level of the fuel before the filter. It was found that the disadvantage of the used filter paper is the fiber wash out process. According to this research it was found that while cleaning fuel from mechanical admixtures it is necessary to take into account the technical condition of the filtering element, and proposal was developed for fuel-filling systems to ensure aviation fuel cleanliness in compliance with regulations.

  18. Improvement of availability of PWR nuclear plants through the reduction of the time required for refueling/maintenance outages

    International Nuclear Information System (INIS)

    Mayers, J.B.; Soth, L.G.

    1978-04-01

    The objective of the project, conducted by Commonwealth Research Corporation and Westinghouse Electric Corporation, is to identify improvements in procedures and equipment which will reduce the time required for refueling/maintenance outages at PWR nuclear power plants. The outage of Commonwealth Edison Zion Station Unit 1 in March through May of 1976 was evaluated to identify those items which caused delays and those work activities that offer the potential for significant improvements that could reduce the overall duration of the outage and achieve an improvement in the plant's availability for power production. Modifications in procedures have been developed and were evaluated during one or more outages in 1977. Conceptual designs have been developed for equipment modifications to the refueling system that could reduce the time required for the refueling portion of the outage. The purpose of the interim report is to describe those conceptual designs and to assess their impact upon future outages. Recommendations are included for the implementation of these equipment improvements in a continuation of this program as a demonstration of plant availability benefits that can be realized in PWR nuclear plants already in operation or under construction

  19. Generalized model development for a cryo-adsorber and 1-D results for the isobaric refueling period

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, V. Senthil [India Science Lab, General Motors Global R and D, Creator Building, International Technology Park, Bangalore 560066 (India); Kumar, Sudarshan [Chemical Sciences and Material Systems Lab, General Motors Global R and D, Warren Technical Center Campus, 30500 Mound Road, Warren, MI 48090 (United States)

    2010-04-15

    We have developed 3-D model equations for a cryo-adsorption hydrogen storage tank, where the energy balance accommodates the temperature and pressure variation of all the thermodynamic properties. We then reduce the 3-D model to the 1-D isobaric system and study the isobaric refueling period, for simplified geometry and charging conditions. The hydrogen capacity evolution predicted by the 1-D axial bed model is significantly different than that predicted by the lumped-parameter model because of the presence of sharp temperature gradients during refueling. The 1-D model predicts a higher hydrogen capacity than the lumped-parameter model. This observation can be rationalized by the fact that a bed with temperature gradients on equilibration should desorb gas, whenever the adsorbed phase entropy is lower than the gas phase entropy. The 1-D analysis of the isobaric refueling period does not show any significant difference in hydrogen capacity evolution among the axial, single and multicartridge annular bed designs. Hence, a multicartridge annular design, though giving a slightly lower pressure drop, does not offer any heat and mass transfer enhancement over the single cartridge design. And, the single cartridge annular design appears to be optimal. (author)

  20. Improvement of availability of PWR nuclear plants through the reduction of the time required for refueling/maintenance outages, Phase 1. Final report

    International Nuclear Information System (INIS)

    Thompson, C.A.

    1978-08-01

    The objective of this project is to identify improvements in procedures and equipment which will reduce the time required for refueling/maintenance outages at PWR nuclear power plants. The outage of Commonwealth Edison Zion Station Unit 1 in March through May of 1976 was evaluated to identify those items which caused delays and those work activities that offer the potential for significant improvements toward reducing its overall duration. Thus, the plant's availability for power production would be increased. Revisions in procedures and some equipment modifications were implemented and evaluated during the Zion Unit 2 refueling/maintenance outage beginning in January 1977. Analysis of the observed data has identified benefits available through improved refueling equipment and also areas where additional new, innovative refueling, or refueling-related equipment should be beneficial. A number of specific design concepts are recommended as a result of Phase 1. In addition, a new master planning mechanism is described for implementation during subsequent planned outages at Zion Station. This final report describes the recommended conceptual designs and planning mechanism and assesses their impact upon future outages. Their effect on savings in refueling time, labor, and radiation exposure is discussed. The estimated economic payoff for these concepts was found to be of such significance that an additional phase of the program is warranted. During this extended phase, a more detailed engineering study should be undertaken to determine the cost of implementation along with more specific estimates of the benefits for PWR plants already in operation or under construction

  1. Key Issues for the control of refueling outage duration and costs in PWR Nuclear Power Plants

    International Nuclear Information System (INIS)

    Degrave, Claude

    2002-01-01

    For several years, EDF, within the framework of the CIDEM1 project and in collaboration with some German Utilities, has undertaken a detailed review of the operating experience both of its own NPP and of foreign units, in order to improve the performances of future units under design, particularly the French-German European Pressurized Reactor (EPR) project. This review made it possible to identify the key issues allowing to decrease the duration of refueling and maintenance outages. These key issues can be classified in 3 categories Design, Maintenance and Logistic Support, Outage Management. Most of the key issues in the design field and some in the logistic support field have been studied and could be integrated into the design of any future PWR unit, as for the EPR project. Some of them could also be adapted to current plants, provided they are feasible and profitable. The organization must be tailored to each country, utility or period: it widely depends on the power production environment, particularly in a deregulation context. (author)

  2. Key issues for the control of refueling outage duration and costs in PWR nuclear power plants

    International Nuclear Information System (INIS)

    Degrave, C.; Martin-Onraet, M.

    2000-01-01

    For several years, EDF, within the framework of the CIDEM project and in collaboration with some German Utilities, has undertaken a detailed review of the operating experience both of its own NPP and of foreign units, in order to improve the performances of future units under design, particularly the French-German European Pressurized Reactor (EPR) project. This review made it possible to identify the key issues allowing to decrease the duration of refueling and maintenance outages. These key issues can be classified in 3 categories: Design; Maintenance and Logistic Support; Outage Management. Most key issues in the design field and some in the logistic support field have been studied and could be integrated into the design of any future PWR unit, as for the EPR project. Some of them could also be adapted to current plants, provided they are feasible and profitable. The organization must be tailored to each country, utility or period: it widely depends on the power production environment, particularly in a deregulation context. (author)

  3. A guidance law for UAV autonomous aerial refueling based on the iterative computation method

    Directory of Open Access Journals (Sweden)

    Luo Delin

    2014-08-01

    Full Text Available The rendezvous and formation problem is a significant part for the unmanned aerial vehicle (UAV autonomous aerial refueling (AAR technique. It can be divided into two major phases: the long-range guidance phase and the formation phase. In this paper, an iterative computation guidance law (ICGL is proposed to compute a series of state variables to get the solution of a control variable for a UAV conducting rendezvous with a tanker in AAR. The proposed method can make the control variable converge to zero when the tanker and the UAV receiver come to a formation flight eventually. For the long-range guidance phase, the ICGL divides it into two sub-phases: the correction sub-phase and the guidance sub-phase. The two sub-phases share the same iterative process. As for the formation phase, a velocity coordinate system is created by which control accelerations are designed to make the speed of the UAV consistent with that of the tanker. The simulation results demonstrate that the proposed ICGL is effective and robust against wind disturbance.

  4. Drogue pose estimation for unmanned aerial vehicle autonomous aerial refueling system based on infrared vision sensor

    Science.gov (United States)

    Chen, Shanjun; Duan, Haibin; Deng, Yimin; Li, Cong; Zhao, Guozhi; Xu, Yan

    2017-12-01

    Autonomous aerial refueling is a significant technology that can significantly extend the endurance of unmanned aerial vehicles. A reliable method that can accurately estimate the position and attitude of the probe relative to the drogue is the key to such a capability. A drogue pose estimation method based on infrared vision sensor is introduced with the general goal of yielding an accurate and reliable drogue state estimate. First, by employing direct least squares ellipse fitting and convex hull in OpenCV, a feature point matching and interference point elimination method is proposed. In addition, considering the conditions that some infrared LEDs are damaged or occluded, a missing point estimation method based on perspective transformation and affine transformation is designed. Finally, an accurate and robust pose estimation algorithm improved by the runner-root algorithm is proposed. The feasibility of the designed visual measurement system is demonstrated by flight test, and the results indicate that our proposed method enables precise and reliable pose estimation of the probe relative to the drogue, even in some poor conditions.

  5. Dual winch nuclear fuel transfer system providing more reliable fuel transfer during refueling operations

    International Nuclear Information System (INIS)

    Meuschke, R.E.; Harper, M.J.; Stefko, D.J.

    1991-01-01

    This paper describes a nuclear power plant having an auxiliary building, a containment building having the wall, a track extending through a transfer tube within the containment wall, and a fuel transfer system for moving fuel assemblies along the track between the auxiliary building side and the containment building side of the containment wall. It comprises: a car having wheels for movement along spaced rails of the track and further having a carrying basket for one or more fuel assemblies; winch means located on the auxiliary building side of the containment wall and above the water level existing over the track during refueling operations to drive the car along the track; first cable means and second cable means extending substantially vertically downward from the winch means to the tack level; first sheave means for directing the first and the second cable means substantially in the horizontal direction along the track; means for securing the first cable means to the car so that winch pulling force on the first cable means drives the car away from the containment building; second sheave means located near the containment end of the transfer tube

  6. HyApproval - Handbook for the approval of hydrogen refuelling stations - First preliminary achievements

    Energy Technology Data Exchange (ETDEWEB)

    Wurster, R.; Vandendungen, G.; Guichard, J.; Molag, M.; Barron, J.; Reijalt, M.; Hill, H.J.; Landinger, H.

    2007-05-15

    The EU-funded project HyApproval [www.hyapproval.org] aims at developing a universal Handbook to facilitate the approval process of Hydrogen Refuelling Stations (HRS) in Europe. The main goal of the HyApproval partnership with 22 partners from Europe and one each from China, Japan and the USA is to provide a Handbook of technical and regulatory requirements to assist authorisation officials, companies and organisations in the safe implementation and operation of HRS. Achievements during the first 15 months: analyses of HRS technology concepts and of equipment and safety distances/ Intermediate Design Paper/ Regulations, Codes and Standards (RCS) review and comparison/ first Handbook draft and first review sessions with HySafe experts/ safety matrix/ identification of accident scenarios/ agreement on safety documentation/ critical review of reliability data from collections and risk studies/ risk assessment (RA) criteria definition and RA/ matrix of acceptability and awareness levels/ database of Fire Associations and First Responders/ calendar of hydrogen events/ general description of CGH{sub 2} interfaces. (au)

  7. Scaling and Parametric Studies of Condensation Oscillation in an In-Containment Refueling Water Storage Tank

    International Nuclear Information System (INIS)

    Lee, Jun Hyung; No, Hee Cheon

    2003-01-01

    The purpose of this paper is to study the condensation oscillation phenomena by steam-jetting into subcooled water through a multihole sparger, implementing a scaling methodology and the similarity correlation between the test facility and model prototype. To corroborate the scaling methodology, various experimental tests were conducted. The thickness of the boundary layer that encloses the steam cavity was found to be equal to the maximum length of the steam cavity formed. Three key scaling parameters were identified and correlated with the maximum amplitude of pressure oscillation: flow restriction coefficient, area ratio of discharge hole to steam cavity, and density ratio of water to steam. Variations of the oscillation amplitude were small when steam-jetting directions were altered. The concept of a reduction factor was introduced for estimating the oscillation amplitude of the multihole sparger with test data from a single-hole sparger. The results of this study can provide suitable guidelines for sparger design utilized in the in-containment refueling water storage tank for the Advanced Power Reactor 1400

  8. Pellet acceleration studies relating to the refuelling of a steady-state fusion reactor

    International Nuclear Information System (INIS)

    Dimock, D.; Jensen, K.; Jensen, V.O.; Joergensen, L.W.; Pecseli, H.L.; Soerensen, H.; Oester, F.

    1975-11-01

    Several methods for refuelling a steady state-fusion reactor have been proposed, and the pellet method seems advantageous if the pellet can be accelerated to the necessary velocity. A study group was formed to analyze this acceleration problem. Two pellet velocity values were considered: 10 4 m/s and 300 m/s. A pellet velocity of 10 4 m/s may be suitable in the case of a reactor, whereas 300 m/s is believed to be a reasonable velocity at which to perform realistic ablation experiments in the near future. A pneumatic acceleration method was found promising. The pressure is either supplied separately or by evaporation of a part of the pellet. In the latter case, a spark behind the pellet should provide the evoporation and the necessary heating of the driving gas. A preliminary test at room temperature with pellets made of beeswax (the density being ten times that of solid hydrogen, and plastic properties similar to those of solid hydrogen) resulted in a pellet velocity of 100 m/s at a modest value of the energy supplied to the spark. (Auth.)

  9. Finite element modelling of different CANDU fuel bundle types in various refuelling conditions

    International Nuclear Information System (INIS)

    Roman, M. R.; Ionescu, D. V.; Olteanu, G.; Florea, S.; Radut, A. C.

    2016-01-01

    The objective of this paper is to develop a finite element model for static strength analysis of the CANDU standard with 37 elements fuel bundle and the SEU43 with 43 elements fuel bundle design for various refuelling conditions. The computer code, ANSYS7.1, is used to simulate the axial compression in CANDU type fuel bundles subject to hydraulic drag loads, deflection of fuel elements, stresses and displacements in the end plates. Two possible situations for the fuelling machine side stops are considered in our analyses, as follows: the last fuel bundle is supported by the two side stops and a side stop can be blocked therefore, the last fuel bundle is supported by only one side stop. The results of the analyses performed are briefly presented and also illustrated in a graphical form. The finite element model developed in present study is verified against test results for endplate displacement and element bowing obtained from strength tests with fuel bundle string and fuelling machine side-stop simulators. Comparison of ANSYS model predictions with these experimental results led to a very good agreement. Despite the difference in hydraulic load between SEU43 and CANDU standard fuel bundles strings, the maximum stress in the SEU43 endplate is about the same with the maximum stress in the CANDU standard endplate. The comparative assessment reveals that SEU43 fuel bundle is able to withstand high flow rate without showing a significant geometric instability. (authors)

  10. Future combustion technology for synthetic and renewable fuels in compression ignition engines (REFUEL). Final report

    Energy Technology Data Exchange (ETDEWEB)

    Aakko-Saksa, P.; Brink, A.; Happonen, M. [and others

    2012-07-01

    This domestic project, Future Combustion Technology for Synthetic and Renewable Fuels in Compression Ignition Engines (ReFuel), was part of a Collaborative Task 'Future Combustion Technology for Synthetic and Renewable Fuels in Transport' of International Energy Agency (IEA) Combustion Agreement. This international Collaborative Task is coordinated by Finland. The three-year (2009-2011) prooject was a joint research project with Aalto University (Aalto), Tampere University of Technology (TUT), Technical Research Centre of Finland (VTT) and Aabo Akademi University (AAU). The project was funded by TEKES, Waertsilae Oyj, Agro Sisu Power, Aker Arctic Technology Oy and the research partners listed above. Modern renewable diesel fuels have excellent physical and chemical properties, in comparison to traditional crude oil based fuels. Purely paraffinic fuels do not contain aromatic compounds and they are totally sulphur free. Hydrotreated Vegetable Oil (HVO) was studied as an example of paraffinic high cetane number (CN) diesel fuels. HVO has no storage and low temperature problems like the fatty acid methyl esters (FAMEs) have. The combustion properties are better than those of crude oil based fuels and FAME, because they have very high cetane numbers and contain no polyaromatic hydrocarbons (PAH). With low HVO density, viscosity and distillation temperatures, these advantageous properties allow far more advanced combustion strategies, such as very high exhaust gas recirculation (EGR) rates or extreme Miller timings, than has been possible with current fossil fuels. The implementation of these advanced combustion technologies, together with the novel renewable diesel fuel, brought significant nitrogen oxides (NO{sub x}), particulate matter (PM) emission reductions with no efficiency losses. (orig.)

  11. Alcohol-fueled vehicles: An alternative fuels vehicle, emissions, and refueling infrastructure technology assessment

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, G.A.; Kerstetter, J.; Lyons, J.K. [and others

    1993-06-01

    Interest in alternative motor vehicle fuels has grown tremendously over the last few years. The 1990 Clean Air Act Amendments, the National Energy Policy Act of 1992 and the California Clean Air Act are primarily responsible for this resurgence and have spurred both the motor fuels and vehicle manufacturing industries into action. For the first time, all three U.S. auto manufacturers are offering alternative fuel vehicles to the motoring public. At the same time, a small but growing alternative fuels refueling infrastructure is beginning to develop across the country. Although the recent growth in alternative motor fuels use is impressive, their market niche is still being defined. Environmental regulations, a key driver behind alternative fuel use, is forcing both car makers and the petroleum industry to clean up their products. As a result, alternative fuels no longer have a lock on the clean air market and will have to compete with conventional vehicles in meeting stringent future vehicle emission standards. The development of cleaner burning gasoline powered vehicles has signaled a shift in the marketing of alternative fuels. While they will continue to play a major part in the clean vehicle market, alternative fuels are increasingly recognized as a means to reduce oil imports. This new role is clearly defined in the National Energy Policy Act of 1992. The Act identifies alternative fuels as a key strategy for reducing imports of foreign oil and mandates their use for federal and state fleets, while reserving the right to require private and municipal fleet use as well.

  12. H2moves.eu Scandinavia. ''Experience from operating a 70 MPa hydrogen refuelling station in Oslo''. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sloth, M.

    2013-02-15

    As part of the H2MOVES Scandinavia project H2 Logic were to construct a large scale hydrogen refuelling station (HRS) in Oslo providing hydrogen for FCEV's from Daimler and Hyundai in the project. The effort has provided extensive results and lessons learned across the entire process from site selection, HRS design and manufacturing to the final installation and operation. An extensive site screening of more than 30 sites in Oslo was firstly conducted to identify the most optimal location for the HRS. A suitable site was identified at the research organisation SINTEF in Gaustad in the western part of Oslo. The location was strategically well located with regards to the other HRS's in the city ensuring good refuelling coverage in Oslo. The HRS was manufactured, installed and operated by H2 Logic based on the company's H2Station technology. The HRS provides 70MPa refuelling in accordance with the SAE J2601, and operation results have confirmed refuelling times consistently below four minutes for a full tank. The HRS includes onsite electrolysis production providing a 20kg/day base load supply, with potentially additional trucking-in of hydrogen up to a total capacity of 200kg/day. The installation of the HRS took in total 10 days, from arrival at site, until first refuelling was conducted. This included local inspection by third parties and authorities as well as several days of hydrogen production and compression to reach the necessary refuelling pressure. Before opening a refuelling recommendation process was successfully conducted by Daimler. The HRS opened on 21st November 2011 and has been operated for 13,5 months during the remainder project period (ending December 2012). The HRS is expected to continue operation beyond the project. Below are shown the major operation results from the HRS during the project: 1) 701 kg dispensed; 2) 313 refueling's conducted; 3) Average availability of 97% during first half of 2012; 4) 53% of all down

  13. Fuel management for off-load annual refuelling of the D-HHT 600 MW(e) reference core

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, U

    1973-03-16

    The reference design for the Dragon-HHT reactor has been optimised for on-load continuous refuelling. The possiblity to operate the reactor on a discontinuous annual reloading schedule might prove of interest and/or necessity. In this paper the influence of an annual 4-batch fuel management scheme on the core physics and fuel cycle economics is investigated. The results of the present investigation give a good indication of the relative merits of the two fuel management schemes. Although a broader parameter survey and a more detailed scrutinising of special cases would be desirable, we feel that the main conclusions are correct and that the principle differences have been elicited.

  14. A contribution to severe accident monitoring: Level measurement of the Incontainment Refueling Water Storage Tank (IRWST), design and qualification

    Energy Technology Data Exchange (ETDEWEB)

    Schumilov, A.; Weber, P.; Esteves, S.

    2012-07-01

    A level measurement sensor for monitoring the water level in the in-containment refueling water storage tank (IRWST) of the EPRTM (generation 3+ pressurized water reactor) during leakage and severe accidents has been developed by AREVA. The development has been accompanied by many functional and material analyses as well as tests to assure the resistivity under extreme conditions, such as high irradiation dose of 5 MGy, increased temperature up to 160 degree centigrade in conjunction with saturated steam conditions. Moreover, the sensor has been designed and experimentally verified to resist the impact of seismic events and airplane crashes as well.

  15. 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

  16. Core and Refueling Design Studies for the Advanced High Temperature Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, David Eugene [ORNL; Ilas, Dan [ORNL; Varma, Venugopal Koikal [ORNL; Cisneros, Anselmo T [ORNL; Kelly, Ryan P [ORNL; Gehin, Jess C [ORNL

    2011-09-01

    The Advanced High Temperature Reactor (AHTR) is a design concept for a central generating station type [3400 MW(t)] fluoride-salt-cooled high-temperature reactor (FHR). The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. This report presents the current status of ongoing design studies of the core, in-vessel structures, and refueling options for the AHTR. The AHTR design remains at the notional level of maturity as important material, structural, neutronic, and hydraulic issues remain to be addressed. The present design space exploration, however, indicates that reasonable options exist for the AHTR core, primary heat transport path, and fuel cycle provided that materials and systems technologies develop as anticipated. An illustration of the current AHTR core, reactor vessel, and nearby structures is shown in Fig. ES1. The AHTR core design concept is based upon 252 hexagonal, plate fuel assemblies configured to form a roughly cylindrical core. The core has a fueled height of 5.5 m with 25 cm of reflector above and below the core. The fuel assembly hexagons are {approx}45 cm across the flats. Each fuel assembly contains 18 plates that are 23.9 cm wide and 2.55 cm thick. The reactor vessel has an exterior diameter of 10.48 m and a height of 17.7 m. A row of replaceable graphite reflector prismatic blocks surrounds the core radially. A more complete reactor configuration description is provided in Section 2 of this report. The AHTR core design space exploration was performed under a set of constraints. Only low enrichment (<20%) uranium fuel was considered. The coated particle fuel and matrix materials were derived from those being developed and demonstrated under the Department of Energy Office of Nuclear Energy (DOE-NE) advanced gas reactor program. The coated particle volumetric packing fraction was restricted to at most 40%. The pressure

  17. Do Lessons in Nature Boost Subsequent Classroom Engagement? Refueling Students in Flight

    Directory of Open Access Journals (Sweden)

    Ming Kuo

    2018-01-01

    afterward, lessons in nature may actually leave students more able to engage in the next lesson, even as students are also learning the material at hand. Such “refueling in flight” argues for including more lessons in nature in formal education.

  18. Autonomous Aerial Refueling Ground Test Demonstration—A Sensor-in-the-Loop, Non-Tracking Method

    Directory of Open Access Journals (Sweden)

    Chao-I Chen

    2015-05-01

    Full Text Available An essential capability for an unmanned aerial vehicle (UAV to extend its airborne duration without increasing the size of the aircraft is called the autonomous aerial refueling (AAR. This paper proposes a sensor-in-the-loop, non-tracking method for probe-and-drogue style autonomous aerial refueling tasks by combining sensitivity adjustments of a 3D Flash LIDAR camera with computer vision based image-processing techniques. The method overcomes the inherit ambiguity issues when reconstructing 3D information from traditional 2D images by taking advantage of ready to use 3D point cloud data from the camera, followed by well-established computer vision techniques. These techniques include curve fitting algorithms and outlier removal with the random sample consensus (RANSAC algorithm to reliably estimate the drogue center in 3D space, as well as to establish the relative position between the probe and the drogue. To demonstrate the feasibility of the proposed method on a real system, a ground navigation robot was designed and fabricated. Results presented in the paper show that using images acquired from a 3D Flash LIDAR camera as real time visual feedback, the ground robot is able to track a moving simulated drogue and continuously narrow the gap between the robot and the target autonomously.

  19. Status of innovative small and medium sized reactor designs 2005. Reactors with conventional refuelling schemes

    International Nuclear Information System (INIS)

    2006-03-01

    research and development (R and D) programmes in Member States, and non-technical factors and arrangements that could facilitate successful development and deployment of innovative reactors within the small-to-medium power range. The annexes, intended mostly for designers and technical managers, provide detailed design descriptions of innovative SMRs under development worldwide and are patterned along a newly developed common format, which makes it possible to identify the design philosophy, objectives and approaches, as well as technical features and non-technical factors and arrangements with a potential to provide solutions in the specific areas of concern associated with future nuclear energy systems. Detailed design descriptions in this report were prepared firsthand by the designers and reviewed, updated and approved for publication by the respective vendors, research and design organizations and academic institutions in Member States. The scope of this report is limited to reactors with conventional, proven in operation refuelling schemes and does not include small reactors that could operate without reloading and shuffling of fuel for a long period, from 10 years and more, with no fresh or spent fuel being stored at the site during reactor operation. Because of a large number of inputs, such reactors would require a separate dedicated publication

  20. Rapid changes in the size of different functional organ and muscle groups during refueling in a long-distance migrating shorebird

    NARCIS (Netherlands)

    Piersma, T; Gudmundsson, GA; Lilliendahl, K; Gudmundsson, Gudmundur A.

    1999-01-01

    The adaptive value of size changes in different organ and muscle groups was studied in red knots (Calidris canutus islandica) in relation to their migration. Birds were sampled on five occasions: at arrival in Iceland in May 1994, two times during subsequent refueling, at departure toward, and on

  1. 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

  2. Design and prototyping of an ionic liquid piston compressor as a new generation of compressors for hydrogen refueling stations

    DEFF Research Database (Denmark)

    Arjomand Kermani, Nasrin

    to investigate the heat transfer phenomena inside the compression chamber; the system performance is evaluated, followed by the design process. The model is developed based on the mass and energy balance of the hydrogen, and liquid bounded by the wall of the compression chamber. Therefore, at each time step...... and positional node, the model estimates the pressure and temperature of the hydrogen and liquid, the temperature of the compression chamber wall, and the amount of heat extracted from the hydrogen directly at the interface between the hydrogen and liquid, and through the wall. The results indicate......, fabrication, and control of the prototype is described in the presented work. The new compressor design has high potential to be used as an alternative to the conventional reciprocating compressors in hydrogen refueling stations, as it provides a simpler design with lower manufacturing costs, higher...

  3. Understanding the design and economics of distributed tri-generation systems for home and neighborhood refueling - Part I: Single family residence case studies

    Energy Technology Data Exchange (ETDEWEB)

    Li, Xuping; Ogden, Joan M. [University of California, Davis, One Shields Avenue, Davis, CA 95616 (United States)

    2011-02-15

    The potential benefits of hydrogen as a transportation fuel will not be achieved until hydrogen vehicles capture a substantial market share. However, although hydrogen fuel cell vehicle (FCV) technology has been making rapid progress, the lack of a hydrogen infrastructure remains a major barrier for FCV adoption and commercialization. The high cost of building an extensive hydrogen station network and the foreseeable low utilization in the near term discourages private investment. Based on the past experience of fuel infrastructure development for motor vehicles, innovative, distributed, small-volume hydrogen refueling methods may be required to refuel FCVs in the near term. Among small-volume refueling methods, home and neighborhood tri-generation systems (systems that produce electricity and heat for buildings, as well as hydrogen for vehicles) stand out because the technology is available and has potential to alleviate consumer's fuel availability concerns. In addition, it has features attractive to consumers such as convenience and security to refuel at home or in their neighborhood. The objective of this paper is to provide analytical tools for various stakeholders such as policy makers, manufacturers and consumers, to evaluate the design and the technical, economic, and environmental performances of tri-generation systems for home and neighborhood refueling. An interdisciplinary framework and an engineering/economic model is developed and applied to assess home tri-generation systems for single family residences (case studies on neighborhood systems will be provided in a later paper). Major tasks include modeling yearly system operation, exploring the optimal size of a system, estimating the cost of electricity, heat and hydrogen, and system CO{sub 2} emissions, and comparing the results to alternatives. Sensitivity analysis is conducted, and the potential impacts of uncertainties in energy prices, capital cost reduction (or increase), government

  4. Understanding the design and economics of distributed tri-generation systems for home and neighborhood refueling - Part I: Single family residence case studies

    International Nuclear Information System (INIS)

    Li, Xuping; Ogden, Joan M.

    2011-01-01

    The potential benefits of hydrogen as a transportation fuel will not be achieved until hydrogen vehicles capture a substantial market share. However, although hydrogen fuel cell vehicle (FCV) technology has been making rapid progress, the lack of a hydrogen infrastructure remains a major barrier for FCV adoption and commercialization. The high cost of building an extensive hydrogen station network and the foreseeable low utilization in the near term discourages private investment. Based on the past experience of fuel infrastructure development for motor vehicles, innovative, distributed, small-volume hydrogen refueling methods may be required to refuel FCVs in the near term. Among small-volume refueling methods, home and neighborhood tri-generation systems (systems that produce electricity and heat for buildings, as well as hydrogen for vehicles) stand out because the technology is available and has potential to alleviate consumer's fuel availability concerns. In addition, it has features attractive to consumers such as convenience and security to refuel at home or in their neighborhood. The objective of this paper is to provide analytical tools for various stakeholders such as policy makers, manufacturers and consumers, to evaluate the design and the technical, economic, and environmental performances of tri-generation systems for home and neighborhood refueling. An interdisciplinary framework and an engineering/economic model is developed and applied to assess home tri-generation systems for single family residences (case studies on neighborhood systems will be provided in a later paper). Major tasks include modeling yearly system operation, exploring the optimal size of a system, estimating the cost of electricity, heat and hydrogen, and system CO 2 emissions, and comparing the results to alternatives. Sensitivity analysis is conducted, and the potential impacts of uncertainties in energy prices, capital cost reduction (or increase), government incentives and

  5. Ensuring safety of fuel cell applications and hydrogen refuelling. Legislation and standards; Polttokennosovellusten ja vetytankkauksen turvallisuuden varmistaminen. Saeaedoeksiae ja standardeja

    Energy Technology Data Exchange (ETDEWEB)

    Nissila, M.; Sarsama, J.

    2013-09-15

    Fuel cell technology is considered a promising alternative in terms of viable energy systems. The advantages of fuel cell systems include a good efficiency rate and the lack of harmful environmental emissions. Factors which may slow down the commercialisation of fuel cell technology, e.g. fuel cell vehicles, include the high price of hydrogen and the insufficiency of the infrastructure required for the distribution of hydrogen. A large proportion of major car manufacturers are committed to introducing fuel cell cars to the market by 2014-2016. In order to ensure a successful market introduction of fuel cell vehicles, this has to be aligned with the development of the necessary hydrogen infrastructure. In the early commercialisation stages of a new technology, it is important to give the public correct, justified and understandable information on the safety of the fuel cell applications, and also on the measures taken to ensure the safety of applications. A lack of necessary information, inaccurate perceptions and prejudices can have an adverse effect on the public acceptance of fuel cell applications. Hazards and potential accidents related to fuel cell systems are mainly associated with the flammable substances (e.g. hydrogen, methane) used as fuel, the high pressure of hydrogen, electrical hazards, and dangers concerning technical systems in general. The fuel cell applications reviewed in this publication are transport applications and stationary applications and the refuelling system of gaseous hydrogen. The publication concentrates on fuel cells using hydrogen as fuel. The publication gives an overview of how EU-legislation (mainly various directives) and Finnish legislation applies to fuel cell systems and applications, and what kind of safety requirements the legislation sets. In addition, a brief overview of safety standards concerning fuel cell systems and hydrogen refuelling is presented. (orig.)

  6. Assessment of occupational exposure to BTEX compounds at a bus diesel-refueling bay: A case study in Johannesburg, South Africa.

    Science.gov (United States)

    Moolla, Raeesa; Curtis, Christopher J; Knight, Jasper

    2015-12-15

    Of increasing concern is pollution by volatile organic compounds, with particular reference to five aromatic hydrocarbons (benzene, toluene, ethyl benzene and two isomeric xylenes; BTEX). These pollutants are classified as hazardous air pollutants. Due to the potential health risks associated with these pollutants, BTEX concentrations were monitored at a bus diesel-refueling bay, in Johannesburg, South Africa, using gas chromatography, coupled with a photo-ionization detector. Results indicate that o-xylene (29-50%) and benzene (13-33%) were found to be the most abundant species of total BTEX at the site. Benzene was within South African occupational limits, but above international occupational exposure limits. On the other hand, occupational concentrations of toluene, ethyl-benzene and xylenes were within national and international occupational limits throughout the monitoring period, based on 8-hour workday weighted averages. Ethyl-benzene and p-xylene concentrations, during winter, correspond to activity at the site, and thus idling of buses during refueling may elevate results. Overall, occupational air quality at the refueling bay is a matter of health concern, especially with regards to benzene exposure, and future reduction strategies are crucial. Discrepancies between national and international limit values merit further investigation to determine whether South African guidelines for benzene are sufficiently precautionary. Copyright © 2015 Elsevier B.V. All rights reserved.

  7. Exact docking flight controller for autonomous aerial refueling with back-stepping based high order sliding mode

    Science.gov (United States)

    Su, Zikang; Wang, Honglun; Li, Na; Yu, Yue; Wu, Jianfa

    2018-02-01

    Autonomous aerial refueling (AAR) exact docking control has always been an intractable problem due to the strong nonlinearity, the tight coupling of the 6 DOF aircraft model and the complex disturbances of the multiple environment flows. In this paper, the strongly coupled nonlinear 6 DOF model of the receiver aircraft which considers the multiple flow disturbances is established in the affine nonlinear form to facilitate the nonlinear controller design. The items reflecting the influence of the unknown flow disturbances in the receiver dynamics are taken as the components of the "lumped disturbances" together with the items which have no linear correlation with the virtual control variables. These unmeasurable lumped disturbances are estimated and compensated by a specially designed high order sliding mode observer (HOSMO) with excellent estimation property. With the compensation of the estimated lumped disturbances, a back-stepping high order sliding mode based exact docking flight controller is proposed for AAR in the presence of multiple flow disturbances. Extensive simulation results demonstrate the feasibility and superiority of the proposed docking controller.

  8. Small Reactors without On-site Refuelling: Neutronic Characteristics, Emergency Planning and Development Scenarios. Final Report of an IAEA Coordinated Research Project

    International Nuclear Information System (INIS)

    2010-09-01

    Small reactors without on-site refuelling have a capability to operate without reloading or shuffling of fuel in their cores for reasonably long periods of time consistent with plant economy and considerations of energy security, with no fresh or spent fuel being stored at the site during reactor operation. In 2009, more than 25 design concepts of such reactors were analyzed or developed in IAEA Member States, representing both developed and developing countries. Small reactors without on-site refuelling are being developed for several reactor lines, including water cooled reactors, sodium cooled fast reactors, lead and lead bismuth cooled reactors, and also include some non-conventional concepts. Most of the concepts of small reactors without on-site refuelling reactors are at early design stages. To make such reactors viable, further research and development (R and D) is necessary, inter alia, to validate long-life core operation, define and validate new robust types of fuel, justify an option of plant location in the proximity to its users, and examine possible niches that such reactors could fill in future energy systems. To further research and development (R and D) in the areas mentioned above and several others, and to facilitate progress in Member States in design and technology development for small reactors without on-site refueling, the IAEA has conducted a dedicated Coordinated Research Project (CRP) entitled 'Small Reactors without On-site Refuelling' (CRPi25001). The project started late in 2004 and, after a review in 2008, was extended for one more year to be ended in 2009. The project has created a network of 18 research institutions from 10 Member States, representing both developed and developing countries. Over the CRP period, collaborative results were achieved for many of the abovementioned research areas. Some studies highlighted new directions of research to be furthered after the CRP completion. Some studies remained the efforts of

  9. Fuel Fraction Analysis of 500 MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel without Refueling

    Science.gov (United States)

    Dewi Syarifah, Ratna; Su'ud, Zaki; Basar, Khairul; Irwanto, Dwi

    2017-01-01

    Nuclear Power Plant (NPP) is one of candidates which can support electricity demand in the world. The Generation IV NPP has fourth main objective, i.e. sustainability, economics competitiveness, safety and reliability, and proliferation and physical protection. One of Gen-IV reactor type is Gas Cooled Fast Reactor (GFR). In this study, the analysis of fuel fraction in small GFR with nitride fuel has been done. The calculation was performed by SRAC code, both Pij and CITATION calculation. SRAC2002 system is a code system applicable to analyze the neutronics of variety reactor type. And for the data library used JENDL-3.2. The step of SRAC calculation is fuel pin calculated by Pij calculation until the data homogenized, after it homogenized we calculate core reactor. The variation of fuel fraction is 40% up to 65%. The optimum design of 500MWth GFR without refueling with 10 years burn up time reach when radius F1:F2:F3 = 50cm:30cm:30cm and height F1:F2:F3 = 50cm:40cm:30cm, variation percentage Plutonium in F1:F2:F3 = 7%:10%:13%. The optimum fuel fraction is 41% with addition 2% Plutonium weapon grade mix in the fuel. The excess reactivity value in this case 1.848% and the k-eff value is 1.01883. The high burn up reached when the fuel fraction is low. In this study 41% fuel fraction produce faster fissile fuel, so it has highest burn-up level than the other fuel fraction.

  10. Biofuels cost developments in the EU27+ until 2030. Full-chain cost assessment and implications of policy options. REFUEL WP4 final report

    International Nuclear Information System (INIS)

    Londo, H.M.; Lensink, S.M.; Deurwaarder, E.P.; Wakker, A.; De Wit, M.; Junginger, M.; Koenighofer, K; Jungmeier, G.

    2008-02-01

    With the rapid developments in the biofuels domain comes the need for biofuel policies that spur their introduction in a responsible way. The REFUEL project, supported by the EU Intelligent Energy Europe programme, develops a road map for biofuels in the EU27+ up to 2030. This WP4 report shows the results of a full-chain analysis of the costs of different biofuels. Effects of different levels of biofuel target setting were analysed, and also the impact of different additional policy measures, such as the introduction of a CO2 pricing mechanism and specific subsidies

  11. Nuclear reactor refuelling machine

    International Nuclear Information System (INIS)

    Peberdy, J.M.

    1975-01-01

    A guide tube for a fuel element assembly gripper unit is radially displaceable on a parallel linkage from the lower end of a vertically disposed rotatable support structure. The gripper unit is longitudinally slidable within the guide tube to enable a fuel element assembly to be fully withdrawn into the guide tube. The gripper unit has a rotatable gripper head for rotating the fuel element assembly about its longitudinal axis. (U.S.)

  12. Nuclear reactor refueling system

    International Nuclear Information System (INIS)

    Wade, E.E.

    1978-01-01

    A system for transferring fuel assemblies between a nuclear reactor core and a fuel storage area while the fuel assembies remain completely submerged in a continuous body of coolant is described. The system comprises an in-vessel fuel transfer machine located inside the reactor vessel and an ex-vessel fuel transfer machine located in a fuel storage tank. The in-vessel fuel transfer machine comprises two independently rotatable frames with a pivotable fuel transfer apparatus disposed on the lower rotatable frame. The ex-vessel fuel transfer machine comprises one frame with a pivotable fuel transfer apparatus disposed thereon. The pivotable apparatuses are capable of being aligned with each other to transfer a fuel assembly between the reactor vessel and fuel storage tank while the fuel assembly remains completely submerged in a continuous body of coolant. 9 claims, 7 figures

  13. Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995; Informe de la Cuarta Recarga de Combustible. Central Laguna Verde. Unidad 1. Abril-Mayo 1995

    Energy Technology Data Exchange (ETDEWEB)

    Mendoza L, A; Flores C, E; Lopez G, C P.F.

    1996-12-31

    The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author).

  14. STAR-H2: a long-refueling interval battery reactor for hydrogen and water supply to cities of developing countries

    International Nuclear Information System (INIS)

    Wade, D. C.; Doctor, R. D.; Sienicki, J. J.; Matonis, D. T.; Faibish, R. S.; Moisseytsev, A. V.

    2004-01-01

    The STAR-H2 concept is devised to attain Gen-IV goals by responding to foreseen mid century needs and market conditions. It is targeted for support of urban centers in developing countries and is designed to fit within a hierarchical hub-spoke architecture based on regional fuel cycle centers, nuclear fuel and hydrogen as long distance energy carriers and distributed electricity generation to mesh with urban energy distribution infrastructures using grid delivery of electricity, hydrogen, potable water, and communications (and sewage return) through a common grid of easements. Long (20 year) refueling interval and full core cassette refueling supported from client country consortia-owned regional fuel cycle (front and back end) service centers, operating under international oversight are intended to make nuclear-based energy security available to countries which don't wish to emplace an indigenous front to back fuel cycle infrastructure. The regional centers, infrequent cassette refueling and full transuranic recycle (both reload and spent fuel cassettes meet the spent fuel standard of self protection) are intended to provide barriers to misuse of materials and facilities for military purposes. Fuel cassette refueling and shipments are conducted by Regional Center personnel. Reactor fissile self sufficient operation and full transuranic multi recycle both extracts the full energy content of the uranium ore, and consigns only fission products to waste. Small to mid sizing permits incremental deployments where capital financing is dear and/or indigenous infrastructure is at an early stage of development. Modular construction, factory fabrication, and delivery of a turnkey heat source reactor to the client's site where a non safety grade balance of plant has already been emplaced by local labor to local standards will facilitate rapid assembly and initiation of revenue generation. The concept employs extensive levels of passive safety to be consistent with a worldwide

  15. Conceptual analyses of neutronic and equilibrium refueling parameters to develop a cost-effective multi-purpose pool-type research reactor using WIMSD and CITVAP codes

    Energy Technology Data Exchange (ETDEWEB)

    Hedayat, Afshin, E-mail: ahedayat@aeoi.org.ir

    2016-12-01

    Highlights: • Introducing a high-beneficent and low-cost multipurpose research reactor. • High technical documents and standard safety issues are introduced coherently. • High effective conceptual neutronic analyses and fuel management strategy. • Gaining high score design criteria and safety margins via 3-D core modeling. • Capacity and capability to produce all medical and industrial radioisotopes. - Abstract: In this paper, neutronic and equilibrium refueling parameters of a multi-purpose cost-effective research reactor have been studied and analyzed. It has been tried to provide periodic and long-term requirements of the irradiating applications coherently. The WIMSD5B and CITVAP codes are used to calculate neutronic parameters and simulate fuel management strategy. The used nuclear data, codes, and calculating methods have been severally benchmarked and verified, successfully. Fundamental concepts, design criteria, and safety issues are introduced and discussed, coherently. Design criteria are selected to gain the most economic benefits per capital costs via minimum required reactor power. Accurate, fast and simplified models have been tried for an integrated decision making and analyses using deterministic codes. Core management, power effects, fuel consumption and burn up effects, and also a complete simulation of the fuel management strategy are presented and analyzed. Results show that the supposed reactor core design can be promisingly suitable in accordance with the commercial multi-purpose irradiating applications. It also retains Operating Limits and Conditions (OLCs) due to standard safety issues, conservatively where safety parameters are calculated using best estimate tools. Such reactor core configuration and integrated refueling task can effectively enhance the Quality Assurance (QA) of the general irradiating applications of the current MTR within their power limits and corresponding OLCs.

  16. The different services carried out on valves during nuclear power plants refuelling outages. To the Valves Integrated Service; La gestion de las diferentes actividades en valvulas durante las paradas. Hacia el Servicio Integral de Valvulas

    Energy Technology Data Exchange (ETDEWEB)

    Laporta, J. M.

    2007-07-01

    The different services carried out on valves during nuclear power plants refuelling outages represent overall one of the activities most interfacing with other refuelling tasks because of the large multidisciplinary teams that participate. Different specialized teams are involved on these activities, mainly on testing, diagnostics and maintenance tasks, performed over the same components, in a sequence of processes closely related with common resources. Under such circumstances, coordination between the different teams intervening and the management of administrative documents and activities in close collaboration with the Control Room is fundamental to ensure that the work is performed in the right sequence avoiding downtimes and optimising the critical path. The integration of these processes and the resources involved allow us to undertake the services globally, forming multidisciplinary teams that optimise resources-fundamentally coordination resources and multi-purpose auxiliary resources-maintaining in all cases the necessary degree of specialisation in keeping with the different tasks making up the Valves Integrated Service. (Author)

  17. Comparative Study on Various Geometrical Core Design of 300 MWth Gas Cooled Fast Reactor with UN-PuN Fuel Longlife without Refuelling

    Science.gov (United States)

    Dewi Syarifah, Ratna; Su'ud, Zaki; Basar, Khairul; Irwanto, Dwi

    2017-07-01

    Nuclear power has progressive improvement in the operating performance of exiting reactors and ensuring economic competitiveness of nuclear electricity around the world. The GFR use gas coolant and fast neutron spectrum. This research use helium coolant which has low neutron moderation, chemical inert and single phase. Comparative study on various geometrical core design for modular GFR with UN-PuN fuel long life without refuelling has been done. The calculation use SRAC2006 code both PIJ calculation and CITATION calculation. The data libraries use JENDL 4.0. The variation of fuel fraction is 40% until 65%. In this research, we varied the geometry of core reactor to find the optimum geometry design. The variation of the geometry design is balance cylinder; it means that the diameter active core (D) same with height active core (H). Second, pancake cylinder (D>H) and third, tall cylinder (Dpower is 300 MWth. First calculation, we calculate survey parameter for UN-PuN fuel with fissile contain from Plutonium waste LWR for each geometry. The minimum power density is around 72 Watt/cc, and maximum power density 114 Watt/cc. After we calculate with various geometry core, when we use the balance geometry, the k-eff value flattest and more stable than the others.

  18. Development and demonstration of techniques for reducing occupational radiation doses during refueling outages. Tasks 7A/7B. Advanced outage management and radiation exposure control

    International Nuclear Information System (INIS)

    1985-03-01

    Objectives of Tasks 7A and 7B were to develop and demonstrate computer based systems to assist plant management and staff in utilizing information more effectively to reduce occupational exposures received as a result of refueling outages, and to shorten the duration of the outage. The Advanced Outage Management (AOM) Tool (Task 7A) is an automated outage planning system specifically designed to meet the needs of nuclear plant outage management. The primary objective of the AOM tool is to provide a computerized system that can manipulate the information typically associated with outage planning and scheduling to furnish reports and schedules that more accurately project the future course of the outage. The Radiation Exposure Control (REC) Tool (Task 7B) is a computerized personnel radiation exposure accounting and management system designed to enable nuclear plant management to project and monitor total personnel radiation exposure on a real-time basis. The two systems were designed to operate on the same computer system and interface through a common database that enables information sharing between plant organizations not typically interfaced. This interfacing provides outage planners with a means of incorporating occupational radiation exposure as a factor for making decisions on the course of an outage

  19. The REFUEL EU road map for biofuels in transport: Application of the project's tools to some short-term policy issues

    International Nuclear Information System (INIS)

    Londo, Marc; Lensink, Sander; Wakker, Andre; Fischer, Guenther; Prieler, Sylvia; van Velthuizen, Harrij; de Wit, Marc; Faaij, Andre; Junginger, Martin; Berndes, Goeran; Hansson, Julia; Egeskog, Andrea; Duer, Henrik; Lundbaek, Jeppe; Wisniewski, Grzegorz; Kupczyk, Adam; Koenighofer, Kurt

    2010-01-01

    The current hot debate on biofuels calls for a balanced and realistic long-term strategy for biofuels. The REFUEL project provides several ingredients for such a strategy. Analyses in this project indicate that domestically produced biofuels can cover a significant share of EU fuel demand in the coming decades, with the EU-12 new member states and Ukraine as most promising regions. This potential can be realised with residual streams and on existing agricultural land, without conversion of e.g. nature reserves. Second generation biofuels are essential for the long-term success of biofuels due to their superior performance in many ways. But generally, the key challenge for the near future would be how to enhance the development of biofuels in a responsible way, i.e. stimulating the production chains with the best performance, and preventing negative impacts e.g., by paying careful attention to possible system impacts of biofuel production such as indirect land use changes and rising food prices. Finally, 2nd generation biofuels require specific policy: the precursor role of 1st generation is overrated, both in technical terms as well as in their role as market precursors. When it comes to synergies, 2nd generation biofuels might benefit more from other developments in the energy sector, such as initiatives in co-firing of biomass for (heat and) power, than from 1st generation biofuels, also because of the public resistance that the latter induce. (author)

  20. Observations and insights from low power and shutdown studies: Grand Gulf Nuclear Power Plant during POS 5 of a refueling outage

    International Nuclear Information System (INIS)

    Whitehead, D.W.; Brown, T.D.; Forester, J.A.

    1995-04-01

    With the recent completion of the documentation of the results from the Grand Gulf Nuclear Power Plant Low Power and Shutdown (LP and S) project funded by the US Nuclear Regulatory Commission (NRC), detailed probabilistic risk assessment (PRA) information from a boiling water reactor (BWR) for a specific time period in LP and S conditions became available for examination. This report contains observations and insights extracted from an examination of: (1) results in the LP and S documentation; (2) the specific models and assumptions used in the LP and S analyses; (3) selected results from the full-power analysis; (4) the experience of the analysts who performed the original LP and S study; and (5) results from sensitivity calculations performed as part of this project to help determine the impact that model assumptions and data values had on the results from the original LP and S analysis. Specifically, this study makes observations on and develops insights from the estimates of core damage frequency and aggregate risk (early fatalities and total latent cancer fatalities) associated with operations during plant operational state (POS) 5 (i.e., basically cold shutdown as defined by Technical Specifications) during a refueling outage for traditional internal events. A discussion of similarities and differences between full power accidents and accidents during LP and S conditions is provided. As part of this discussion, core damage frequency and risks results are presented on a per hour and per calendar year basis, allowing alternative perspectives on both the core damage frequency and risk associated with these two operational states

  1. LiquidPower-1. Development and proof-of-concept of core methanol reformer for stationary and motive fuel cell systems and hydrogen refuelling stations. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Krogsgaard, J.; Mortensen, Henrik [H2 Logic A/S, Herning (Denmark); Skipper, T. [Dantherm Power A/S, Hobro (Denmark)

    2013-03-15

    LiquidPower-1 has developed laboratory test systems for methanol reforming and tested reformers from four different suppliers. This has contributed to determining the state-of-the-art level for methanol reforming and enabled an update of the LiquidPower R and D Roadmap onwards a commercialisation of the technology. The project has achieved the following results: 1) A detailed technical specification of methanol reformers for the fuel cell back-up power and hydrogen refueling station markets has been conducted; 2) Laboratory test systems for methanol reformers has been developed and established at Dantherm Power and H2 Logic; 3) Initial test of reformers from four suppliers has been conducted - with two suppliers being selected for continued tests; 4) Extensive laboratory tests conducted of reformers from two suppliers, with the aim to determine state-of-the-art for price, efficiency, capacity and lifetime. Several errors and break-downs were experienced during the test period, which revealed a need for further R and D to improve lifetime and stability; 5) The LiquidPower F and U Roadmap has been updated. Reformer TCO targets (Total Cost of Operation) for each of the markets have been calculated including updated targets for efficiency and cost. These targets also serve as the main ones to be pursued as part of the continued R and D roadmap execution. Compared to the previous edition of the Roadmap, the project has confirmed the viability of methanol reforming, but also revealed that stability and lifetime needs to be addressed and solved before commencing commercialization of the technology. If the Roadmap is successful a commercialization can commence beyond 2015. (Author)

  2. An optimal hydrogen control analysis for the in-containment refueling storage tank (IRWST) of the Korean next generation reactor (KNGR) containment under severe accidents

    International Nuclear Information System (INIS)

    Byung-Chul, Lee; Hee-Jin, Ko; Se-Won, Lee

    2001-01-01

    Under severe accidents that a large amount of hydrogen is expected to release, the In-Containment Refueling Water Storage Tank (IRWST) air space has more worse condition with respect to the hydrogen control since, as one of hydrogen source compartment, normally it is separated from the other compartments and has relatively small volume. The hydrogen concentrations in the IRWST gas space, when the hydrogen was directly released into this area, were analyzed using the MAAP4 code in order to investigate if locally very high concentrations could be reduced so that inadvertent detonation or detonation-to-deflagration (DDT) in this area might be prevented. For this purpose, the thermo-hydraulic and combustion phenomena being capable of occurring in the IRWST were also considered. As a result of numerical calculations with 12-compartment containment model, the time duration that the flammable gas mixture was formed was greatly decreased via oxygen-starved or steam-rich conditions, although instantaneously peak concentration itself could not be avoided. Moreover, if the diffusion flame or steam stripping can be occurred in the IRWST, it was expected to have more chance to control the hydrogen in the IRWST gas space. After the hydrogen finished to be rapidly released, the hydrogen in this area could be controlled by the PARs' hydrogen depletion and by igniter's deliberate burning. Especially, the review on the analyses for two typical, but most probable sequences of quite a different hydrogen release modes gives an insight that the flammable gas mixture in the IRWST can be avoid by rapid depressurization operation, which is recommendable for being implemented into accident management program. (authors)

  3. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 5: Analysis of core damage frequency from seismic events for plant operational state 5 during a refueling outage

    International Nuclear Information System (INIS)

    Budnitz, R.J.; Davis, P.R.; Ravindra, M.K.; Tong, W.H.

    1994-08-01

    In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Sandia National Laboratories studying a boiling water reactor (Grand Gulf), and the other at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1). Both the Sandia and Brookhaven projects have examined only accidents initiated by internal plant faults---so-called ''internal initiators.'' This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling outage conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Grand Gulf. All of the many systems modeling assumptions, component non-seismic failure rates, and human effort rates that were used in the internal-initiator study at Grand Gulf have been adopted here, so that the results of the study can be as comparable as possible. Both the Sandia study and this study examine only one shutdown plant operating state (POS) at Grand Gulf, namely POS 5 representing cold shutdown during a refueling outage. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POS 5. The results of the analysis are that the core-damage frequency for earthquake-initiated accidents during refueling outages in POS 5 is found to be quite low in absolute terms, less than 10 -7 /year

  4. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Analysis of core damage frequency from internal events for plant operational state 5 during a refueling outage. Internal events appendices K to M

    International Nuclear Information System (INIS)

    Forester, J.; Yakle, J.; Walsh, B.; Darby, J.; Whitehead, D.; Staple, B.; Brown, T.

    1994-07-01

    This report provides supporting documentation for various tasks associated with the performance of the probabilistic risk assessment for Plant Operational State 5 (approximately Cold Shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143. The report contains the following appendices: K - HEP Locator Files; L - Supporting Information for the Plant Damage State Analysis; M - Summary of Results from the Coarse Screening Analysis - Phase 1A

  5. LINK2009 Phase 1: Development of 2. generation fuel cell vehicles and hydrogen refueling station. Final report; LINK2009 fase 1: Udvikling af 2. gen. braendselscelle koeretoejer og brinttankstation. Slutrapport

    Energy Technology Data Exchange (ETDEWEB)

    2010-03-15

    LINK2009 project was to develop 2nd gen. technologies fuel cell systems for vehicles and 350bar hydrogen refueling stations. Also the LINK2009 project were to ensure a continuously positioning of Denmark and the Scandinavian Region within hydrogen for transport and continue to attract international car manufacturers to conduct demonstration and later market introduction in the region. The LINK2009 project is divided in two phases where this first phase only deals with the development of the 2nd generation technologies, whereas the following phase 2 will include the demonstration hereof as well as additional research activities. This Report describes the results of the phase 1 that was commenced in summer 2008 and ended in late 2009. Phase 1 has resulted in the development of new 2nd generation fuel cell technology for use in a city car and a service vehicle. Stated targets for price and efficiency have been reached and the following demonstration in Phase 2 is to confirm reaching of life time targets. The efficiency of the fuel cell system for the city car has been measured to be 42-48% at a power delivery of respectively 10kW and 2kW, which is significantly above the target of >40%. System simplifications and selection of new components have enabled a 50% reduction in the kW price for the fuel cell system, including 700bar hydrogen storage, now totalling Euro 4.500/kW. This creates sufficient basis for conducting demonstration of the system in vehicles. 9 vehicles are planned to be demonstrated in the following phase 2. Additional 8 vehicles were put in operation in Copenhagen in November 2009. Phase 1 has conducted development of 2nd gen. hydrogen refuelling technology that has resulted in concepts for both 350bar and 700bar refuelling as well as a concept for onsite hydrogen production at refuelling stations. In separate projects the developed 350bar technology has been brought to use in a newly established hydrogen station in Copenhagen, and the hydrogen

  6. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internally induced flooding events for Plant Operational State 5 during a refueling outage. Volume 4

    International Nuclear Information System (INIS)

    Dandini, V.; Staple, B.; Kirk, H.; Whitehead, D.; Forester, J.

    1994-07-01

    An estimate of the contribution of internal flooding to the mean core damage frequency at the Grand Gulf Nuclear Station was calculated for Plant Operational State 5 during a refueling outage. Pursuant to this objective, flood zones and sources were identified and flood volumes were calculated. Equipment necessary for the maintenance of plant safety was identified and its vulnerability to flooding was determined. Event trees and fault trees were modified or developed as required, and PRA quantification was performed using the IRRAS code. The mean core damage frequency estimate for GGNS during POS 5 was found to be 2.3 E-8 per year

  7. Nuclear refueling platform drive system

    International Nuclear Information System (INIS)

    Busch, F.R.; Faulstich, D.L.

    1992-01-01

    This patent describes a drive system. It comprises: a gantry including a bridge having longitudinal and transverse axes and supported by spaced first and second end frames joined to fist and second end frames joined to first and second drive trucks for moving the bridge along the transverse axis; first means for driving the first drive truck; second means for driving the second drive truck being independent from the first driving means; and means for controlling the first and second driving means for reducing differential transverse travel between the first and second drive trucks, due to a skewing torque acting on the bridge, to less than a predetermined maximum, the controlling means being in the form of an electrical central processing unit and including: a closed-loop first velocity control means for controlling velocity of the first drive truck by providing a first command signal to the first driver means; a close loop second velocity control means for controlling velocity of the second drive truck by providing a second command signal to the second driving means; and an auxiliary closed-loop travel control means

  8. Nuclear reactor refuelable in space

    International Nuclear Information System (INIS)

    El-Genk, M.S.; Buden, D.; Mims, J.E.

    1992-01-01

    This patent describes a gas cooled nuclear reactor suitable for use in space. It comprises a lightweight structure comprising a plurality of at least three sections, each sector comprising a container for a reactor core separate and distinct from the reactor cores of the other sectors, each sector being capable of operating on its own and in cooperation with one or more of the other sectors and each sector having a common juncture with every other structure; and means associated with each sector independently introducing gas coolant into and extracting coolant from each sector to cool the core therein, wherein in event of failure of the cooling system of a core in a sector, one or more of the other sectors comprise means for conducting heat away from the failed sector core and means for convecting the heat away, and wherein operation of the one or more other sectors is maintained

  9. ENUSA activity in refuelling services

    International Nuclear Information System (INIS)

    Rodriguez Aycar, M.; Alvarez Rodriguez, P.

    2010-01-01

    This service includes the handling of fresh and irradiated fuel, the combination of various inspection techniques for detection of failed rods, ultrasonic surface cleaning, the repair of damaged assemblies, visual inspections and a wide range of of tests and inspections related to the reliability of mechanical components of fuel assemblies and to the programs to monitor its performance. (Author)

  10. Refuelling machine for nuclear reactor

    International Nuclear Information System (INIS)

    Shumyakin, E.P.; Sabir-de-Ribas, K.I.; Druzhinsky, I.A.; Shishov, G.P.; Andreichikov, B.I.

    1979-01-01

    The proposed manipulating means consists of housing, wherein a gripping means is arranged to grip a fuel assembly being transferred. The gripping means is coupled to a drive having a chain which is in contact with a sprocket mounted on an axle arranged in the sealed housing. The driving force of the drive is transmitted to the gripping means. The driving force is controlled by a force regulator mounted on the gripping means. The force regulator comprises two force tranducers mounted on the sealed housing, and a spring suspension member installed in the gripping means. Some clearance is allowed where the drive sprocket axle is secured in the walls of the sealed housing. The ends of the axle extend outside the sealed housing and are coupled to sensitive elements of the force transducers

  11. Assessment of Refueling Hose Visibility

    Science.gov (United States)

    2012-10-01

    order to make inteligent decisions regarding hose replacement or hose cleaning one needs to look at the individual reflection coefficients not just... artificial lighting used to illuminate the hose does not satisfy the specular reflection geometry for the pilot’s view angle of the hose. Also, from

  12. Aerial Refueling Clearance Process Guide

    Science.gov (United States)

    2014-08-21

    using multinational/bi-lateral agreements such as the ATARES Agreement, cross servicing agreements, replacement in kind agreements, Foreign Military...Lighting 8.7.8 External Paint Scheme 8.8 External Weapons/Drop Tanks 9.0 Physical /Aerodynamic Influences 9.1 Boom Clear Path To Receptacle dhkARSAG DOC...Cold Nose Sw. 8.5 External Fuel Tanks 9.0 Physical /Aerodynamic Influence R. 9.1 Probe Clear Path ie: Obstructions, Instruments etc. 9.2 Drogue Hookup

  13. Use of an advanced document system in post-refuelling updating of nuclear power plant documentation; Utilizacion de un sistema documental avanzado en la actualizacion de documentacion post recarga

    Energy Technology Data Exchange (ETDEWEB)

    Puech Suanzes, P; Cortes Soler, M [Empresarios Agrupados, A.I.E., Madrid (Spain)

    1993-12-15

    This paper discusses the results of the extensive use of an advanced document system to update documentation prepared by traditional methods and affected by changes in the period between two plant refuellings. The implementation of a system for the capture, retrieval and storage of drawings using optical discs is part of a plan to modernize production and management tools and to thus achieve better control of document configuration. These processes are consequently optimized in that: 1. The deterioration of drawings is detained with the help of an identical, updated, legible, reliable support for all users. 2. The time required to update documentation is reduced. Given the large number of drawings, the implementation method should effectively combine costs and time. The document management tools ensure optical disc storage control so that from the moment a drawing resides in the system, any modification to it is made through the system utilities, thus ensuring quality and reducing schedules. The system described was used to update the electrical drawings of Almaraz Nuclear Power Plant. Changes made during the eighth refuelling of Unit I were incorporated and the time needed to issue the updated drawings was reduced by one month. (author)

  14. Louisiana SIP: LAC 33:III Ch 2132. Stage II Vapor Recovery Systems for Control of Vehicle Refuelling Emissions at Gasoline Dispensing Facilities; SIP effective 2011-08-04 (LAd34) and 2016-02-29 (LAd47) to 2017-09-27

    Science.gov (United States)

    Louisiana SIP: LAC 33:III Ch 2132. Stage II Vapor Recovery Systems for Control of Vehicle Refuelling Emissions at Gasoline Dispensing Facilities; SIP effective 2011-08-04 (LAd34) and 2016-02-29 (LAd47) to 2017-09-27

  15. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J

    Energy Technology Data Exchange (ETDEWEB)

    Yakle, J. [Science Applications International Corp., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Whitehead, D.; Staple, B. [Sandia National Labs., Albuquerque, NM (United States)

    1994-06-01

    This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143.

  16. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J

    International Nuclear Information System (INIS)

    Yakle, J.; Darby, J.; Whitehead, D.; Staple, B.

    1994-06-01

    This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143

  17. New signal acquisition and processing system for the execution of initial criticality after refueling and physical tests at low power in Angra-2, with the incorporation of the real time resolution of the inverse point kinetic equation - IPK

    Energy Technology Data Exchange (ETDEWEB)

    Júnior, Décio Brandes M.F.; Oliveira, Mônica Georgia N.; Silva, Cristiano da, E-mail: deciobr@eletronuclear.gov.br, E-mail: mongeor@eletronuclear.gov.br, E-mail: cdsilva@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Departamento DDD.O - Física de Reatores

    2017-07-01

    The goal of this work is present the new System of Acquisition and Signal Processing for the execution of the initial criticality after refueling and physical tests at low power with the incorporation of the real time resolution of Inverse Point Kinetic Equations (IPK). The system was developed using cRIO 9082 hardware (compactRIO), which is a programmable logic controller (PLC) and, the National Lab's LabVIEW programming language. The developed system enabled a better visualization and monitoring interface of the neutron flux evolution during the first criticality of cycle and following the low power physical tests, which allows the Reactor Physics Group and Reactor Operators of Angra 2 guide faster and accurately the reactivity variations at physical tests. The digital reactivity meter developed reinforces in Angra-2 the set of operational practices of reactivity management. (author)

  18. New signal acquisition and processing system for the execution of initial criticality after refueling and physical tests at low power in Angra-2, with the incorporation of the real time resolution of the inverse point kinetic equation - IPK

    International Nuclear Information System (INIS)

    Júnior, Décio Brandes M.F.; Oliveira, Mônica Georgia N.; Silva, Cristiano da

    2017-01-01

    The goal of this work is present the new System of Acquisition and Signal Processing for the execution of the initial criticality after refueling and physical tests at low power with the incorporation of the real time resolution of Inverse Point Kinetic Equations (IPK). The system was developed using cRIO 9082 hardware (compactRIO), which is a programmable logic controller (PLC) and, the National Lab's LabVIEW programming language. The developed system enabled a better visualization and monitoring interface of the neutron flux evolution during the first criticality of cycle and following the low power physical tests, which allows the Reactor Physics Group and Reactor Operators of Angra 2 guide faster and accurately the reactivity variations at physical tests. The digital reactivity meter developed reinforces in Angra-2 the set of operational practices of reactivity management. (author)

  19. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 2, Part 1C: Analysis of core damage frequency from internal events for plant operational State 5 during a refueling outage, Main report (Sections 11--14)

    International Nuclear Information System (INIS)

    Whitehead, D.; Darby, J.; Yakle, J.

    1994-06-01

    This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power analyses performed on Grand Gulf

  20. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 2: Internal Events Appendices A to H

    International Nuclear Information System (INIS)

    Darby, J.; Whitehead, D.; Staple, B.; Dandini, V.

    1994-06-01

    This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power analyses performed on Grand Gulf

  1. Evaluation of potential severe accidents during Low Power and Shutdown Operations at Grand Gulf, Unit 1. Volume 2, Part 1B: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage, Main report (Section 10)

    International Nuclear Information System (INIS)

    Whitehead, D.; Darby, J.; Yakle, J.

    1994-06-01

    This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power performed on Grand Gulf. This document, Volume 2, Part 1B, presents chapters Section 10 of this report, Human Reliability Analysis

  2. Achievement report for fiscal 2000 on the phase II research and development for hydrogen utilizing international clean energy system technology (WE-NET). Task 7. Development of hydrogen refueling station; 2000 nendo suiso riyo kokusai clean energy system gijutsu (WE-NET) dai 2 ki kenkyu kaihatsu. Task 7. Suiso kyokyu station no kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    This paper describes the achievements in fiscal 2000 from the development of hydrogen refueling stand-alone stations for hydrogen fueled automobiles in the WE-NET. Supply capacity of practical size of 1/10, 30 Nm{sup 3} was selected as the object. For the natural gas reformed type hydrogen generator, discussions were given on design and manufacture of a reforming unit and a PSA device. The PCT diagram method was discussed to estimate the capacity of a hydrogen absorbing alloy type storing facility. Interface between fuel cell driven automobiles and the station was adjusted. For the solid polymer electrolyte water decomposition type, safety measures were discussed with a high-pressure filling system kept in mind. Detailed design was made on a water decomposing hydrogen generator. Fabrication was completed on the hydrogen absorbing alloy type storing facility, and verifications were given on the storage amount, hydrogen absorbing speed, and discharge capability. In the high-pressure refueling system, temperature rise was simulated at a pressure of 35 MPa. Refueling for ten minutes raised the gas temperature by 75 degrees C, and the container surface by 65 degrees C. Local temperature rise was forecasted in the actual work, which is a future discussion assignment. An outline method was discussed for the verification test. (NEDO)

  3. Improving the refueling cycle of a WWER-1000 using cuckoo search method and thermal-neutronic coupling of PARCS v2.7, COBRA-EN and WIMSD-5B codes

    Energy Technology Data Exchange (ETDEWEB)

    Yarizadeh-Beneh, M.; Mazaheri-Beni, H.; Poursalehi, N., E-mail: n_poursalehi@sbu.ac.ir

    2016-12-15

    Highlights: • The cuckoo search algorithm is applied to the loading pattern optimization of a nuclear reactor core. • Calculations during the cycle show a good agreement between results and reference for the original LP. • Results indicate the efficient performance of cuckoo search approach coupled with thermal-neutronic solvers. • Neutronic parameters of proposed core pattern are improved relative to original core pattern. - Abstract: The fuel loading pattern optimization is an important process in the refueling design of a nuclear reactor core. Also the analysis of reactor core performance during the operation cycle can be a significant step in the core loading pattern optimization (LPO). In this work, for the first time, a new method i.e. cuckoo search algorithm (CS) has been applied to the fuel loading pattern design of Bushehr WWER-1000 core. In this regard, two objectives have been chosen for finding the best configuration including the improvement of operation cycle length associated with flattening the radial power distribution of fuel assemblies. The core pattern optimization has been performed by coupling the CS algorithm to thermal-neutronic codes including PARCS v2.7, COBRA-EN and WIMSD-5B for earning desired parameters along the operation cycle. The calculations have been done for the beginning of cycle (BOC) to the end of cycle (EOC) states. According to numerical results, the longer operation cycle for the semi-optimized loading pattern has been achieved along with less power peaking factor (PPF) in comparison to the original core pattern of Bushehr WWER-1000. Gained results confirm the efficient and suitable performance of the developed program and also the introduced CS method in the LPO of a nuclear WWER type.

  4. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Main report and appendices, Volume 6, Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Brown, T.D.; Kmetyk, L.N.; Whitehead, D.; Miller, L. [Sandia National Labs., Albuquerque, NM (United States); Forester, J. [Science Applications International Corp., Albuquerque, NM (United States); Johnson, J. [GRAM, Inc., Albuquerque, NM (United States)

    1995-03-01

    Traditionally, probabilistic risk assessments (PRAS) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Recent studies and operational experience have, however, implied that accidents during low power and shutdown could be significant contributors to risk. In response to this concern, in 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The program consists of two parallel projects being performed by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). The program objectives include assessing the risks of severe accidents initiated during plant operational states other than full power operation and comparing the estimated risks with the risk associated with accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program is that of a Level-3 PRA. The subject of this report is the PRA of the Grand Gulf Nuclear Station, Unit 1. The Grand Gulf plant utilizes a 3833 MWt BUR-6 boiling water reactor housed in a Mark III containment. The Grand Gulf plant is located near Port Gibson, Mississippi. The regime of shutdown analyzed in this study was plant operational state (POS) 5 during a refueling outage, which is approximately Cold Shutdown as defined by Grand Gulf Technical Specifications. The entire PRA of POS 5 is documented in a multi-volume NUREG report (NUREG/CR-6143). The internal events accident sequence analysis (Level 1) is documented in Volume 2. The Level 1 internal fire and internal flood analyses are documented in Vols 3 and 4, respectively.

  5. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Main report and appendices, Volume 6, Part 1

    International Nuclear Information System (INIS)

    Brown, T.D.; Kmetyk, L.N.; Whitehead, D.; Miller, L.; Forester, J.; Johnson, J.

    1995-03-01

    Traditionally, probabilistic risk assessments (PRAS) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Recent studies and operational experience have, however, implied that accidents during low power and shutdown could be significant contributors to risk. In response to this concern, in 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The program consists of two parallel projects being performed by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). The program objectives include assessing the risks of severe accidents initiated during plant operational states other than full power operation and comparing the estimated risks with the risk associated with accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program is that of a Level-3 PRA. The subject of this report is the PRA of the Grand Gulf Nuclear Station, Unit 1. The Grand Gulf plant utilizes a 3833 MWt BUR-6 boiling water reactor housed in a Mark III containment. The Grand Gulf plant is located near Port Gibson, Mississippi. The regime of shutdown analyzed in this study was plant operational state (POS) 5 during a refueling outage, which is approximately Cold Shutdown as defined by Grand Gulf Technical Specifications. The entire PRA of POS 5 is documented in a multi-volume NUREG report (NUREG/CR-6143). The internal events accident sequence analysis (Level 1) is documented in Volume 2. The Level 1 internal fire and internal flood analyses are documented in Vols 3 and 4, respectively

  6. Handling of Deuterium Pellets for Plasma Refuelling

    DEFF Research Database (Denmark)

    Jensen, Peter Bjødstrup; Andersen, Verner

    1982-01-01

    The use of a guide tube technique to inject pellets in pellet-plasma experiments is described. The effect of the guide tube on the mass and speed of a slowly moving pellet ( nu approximately 150 m s-1) is negligible. To improve the divergence in trajectories of the pellets on leaving the guide tube...

  7. Autonomous Refueling of Unmanned Vehicles at Sea

    Science.gov (United States)

    2008-03-28

    As seen in Figure 3, a floating sponson, similar to the outside flotation collar on a RIB, is towed off the stern of the parent ship with a tow...V. Minnick, Thomas G. Beukema, Wojciech Kauczynski, Andrew L. Silver , and Christopher Cleary, “Stern Boat Deployment Systems and Operability

  8. Prediction of iodine activity peak during refuelling

    International Nuclear Information System (INIS)

    Hozer, Z.; Vajda, N.

    2001-01-01

    The increase of fission product activities in the primary circuit of a nuclear power plant indicates the existence of defects in some fuel rods. The power change leads to the cooling down of the fuel and results in the fragmentation of the UO 2 pellets, which facilitates the release of fission products from the intergranular regions. Furthermore the injection of boric acid after shutdown will increase the primary activity, due to the solution of deposited fission products from the surface of the core components. The calculation of these phenomena usually is based on the evaluation of activity measurements and power plant data. The estimation of iodine spiking peak during reactor transients is based on correlation with operating parameters, such as reactor power and primary pressure. The approach used in the present method was applied for CANDU reactors. The VVER-440 specific correlations were determined using the activity measurements of the Paks NPP and the data provided by the Russian fuel supplier. The present method is used for the evaluation of the iodine isotopes, as well as the noble gases. A numerical model has been developed for iodine spiking simulation and has been validated against several shutdown transients, measured at Paks NPP. (R.P.)

  9. Automated Aerial Refueling Concept of Operations

    Science.gov (United States)

    2017-06-09

    and their associated contractors . This document is suitable for release in the public domain; it may be included in DOD and NATO databases such as...5.3.5 TENSION DISCONNECT (BOOM/RECEPTACLE ONLY) ..................22 5.3.6 FUEL LEAKAGE...Navigation System (INS) technology to provide high -availability, high integrity, four dimensional guidance. A robust datalink will be needed with the

  10. Air-to-Air UAV Aerial Refueling

    Data.gov (United States)

    National Aeronautics and Space Administration — Armstrong researchers, in cooperation with Northrop Grumman Corporation and the Defense Advanced Research Projects Agency (DARPA) demonstrated autonomous aerial...

  11. Reference Design for a Simple, Durable and Refuelable Interplanetary Spacecraft

    Science.gov (United States)

    McConnell, B. S.; Tolley, A. M.

    This article describes a reference design for interplanetary vessels, composed mostly of water, that utilize simplified RF engines for low thrust, long duration propulsion, and hydrogen peroxide for short duration, high thrust burns. The electrothermal engines are designed to heat a wide range of liquid materials, possibly also milled solids or surface dusts. The system emphasizes simple components and processes based on older technologies, many well known since the 1960s, that are understandable, can process a variety of materials, and are easily serviced in flight. The goal is to radically simplify systems and their inter-dependencies, to a point where a reasonably skilled person can learn to operate these vessels, not unlike a sailboat, and to eliminate many design and testing bottlenecks in their construction. The use of water, or hydrogen peroxide generated in situ from that water, is multiply advantageous because it can be used for structure, consumption, irrigation, radiation and debris shielding, and thermal regulation, and thus greatly reduce dead weight by creating an almost fully consumable ship. This also enables the ship to utilize a wide range of in situ materials, and eventually obtain reaction mass from lower gravity sites. The ability to switch between low thrust, constant power and high thrust, short duration maneuvers will enable these ships to travel freely and reach many interesting destinations throughout the solar system. One can think of them as “spacecoaches”, not unlike the prairie schooners of the Old West, which were rugged, serviceable by tradesmen, and easily maintained.

  12. Device for swinging a gripper in a refueling machine

    International Nuclear Information System (INIS)

    Saima, Toru; Imada, Takahiko.

    1976-01-01

    Object: To provide a device, which can eliminate runout of a telescopic mast when swung for driving, which can eliminate the necesssity of balancing the mast and which is good in vertical precision. Structure: A toothed wheel having a hole through which a telescopic mast is inserted is meshed with a pinion rotated by a driving device to constitute a driving and transmitting mechanism. A coupling mechanism for coupling the toothed wheel and the telescopic mast comprises a bellows having a suitable lateral rigidity and washers securely fastended to opposite ends of said bellows, the washer being fixed to the lower surface of the toothed wheel and the washer fixed to the telescopic mast, respectively, by means of screws. The coupling mechanism is flexed in response to oscillation of the telescopic mast and has a suitable lateral rigidity to transmit rotational motion of the toothed wheel to the telescopic mast. (Kawakami, Y.)

  13. Approach to shortening duration of nuclear plant refueling outage

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Yoshiharu; Nakanishi, Tooru [Mitsubishi Heavy Industries Ltd., Kobe (Japan). Kobe Shipyard and Machinery Works; Yoshihara, Seiichi; Kanbara, Masayuki; Yamanaka, Misao; Shimizu, Takeshi

    1998-07-01

    This paper summarizes the mission role of the MHI in-house project team for a shorter outage duration for PWR plants operating in Japan and its results. The major tasks of project team are benchmarking to develop outage performance goals, and develop recommendation packages for outage enhancement covering field procedures and tooling betterment. An optimization study for maintenance tasks was also carried out. This paper highlights the results of efforts the activities of the project team. (author)

  14. Device for refueling a non-stationary nuclear reactor

    International Nuclear Information System (INIS)

    Vogt, F.; Kostrzewa, S.; Siebert, W.

    1979-01-01

    The manipulating pool containing magazines for fuel elements and a manipulator is put on the lower part of the naval reactor pressure vessel after the closure of the latter has been removed. Subsequently, the reactor vessel as well as the manipulating pool are flooded up to a certain level. The outer diameter of the manipulating pool being larger than the opening of the closure, a ledge is formed on which the magazines are installed, distributed over the circumference. By this means the inner space remains free for the movement of the manipulator. The manipulating pool may also consist of two concentric cylinder pools so that there may be obtained partial radiation shielding by means of non-demineralized water or sea water in the annulus. (DG) [de

  15. Remotely Piloted Aircraft (RPA) Performing the Air Refueling Mission

    Science.gov (United States)

    2012-06-01

    point stating that it can also be applied to program planning and administration. Adler and Ziglio (1996) support Delbeq’s et al. (1975) assertion...experts in a group decision making setting; both qualitative and quantitative methods can be used (Skulmoski et al., 2007). According to Adler and...Results and Analysis “It requires a very unusual mind to undertake the analysis of the obvious.” - Alfred North Whitehead Expert Panel Composition

  16. Standardized Technical Data Survey (STDS) for Aerial Refueling

    Science.gov (United States)

    2016-09-06

    enter text. c Distance (from nozzle tip) where measured (Inches) Click here to enter text. d Provide a fuel flow versus pressure curve for all pumping ...AUTHORIZED FUELS 9. MAXIMUM FUEL ONLOAD RATE (WHERE MEASURED) Ref. 2 (ARSAG Doc 03-00-03R) 10. MAXIMUM RATE OF FUEL DUMP (Optional) 11. FUEL VENT CAPABILITY...tank and all tanks filling. ☐Attached to Survey ☐ Not Available a Maximum rate of fuel dump (GPM) Click here to enter text. a Has the vent be certified

  17. Home of the 151st Air Refueling Wing

    Science.gov (United States)

    History HRA Alley Public Affairs SAPR Units Contact Us Search 151st ARW: 151st ARW The Roland R. Wright woman in the profession of arms President Trump visits Roland R. Wright Air National Guard Base 151st Commentaries Women's History Month: looking around as important as looking back Veterans Day: Pay tribute with

  18. Refueling the STEM and Special Education Teacher Pipelines

    Science.gov (United States)

    Goldhaber, Dan; Krieg, John; Theobald, Roddy; Brown, Nate

    2016-01-01

    Improving the quality of the teacher workforce is high on the nation's education policy agenda, but school systems continue to face difficulties in staffing STEM and special education classrooms with qualified teachers. This article documents the mismatch between the supply and demand of STEM and special education teachers in Washington State,…

  19. Air Force KC-X Aerial Refueling Tanker Aircraft Program

    National Research Council Canada - National Science Library

    2007-01-01

    Why You Should Read This Report. This report discusses efforts by Air Force acquisition officials to develop an acquisition strategy to ensure that the Air Force maintains competition throughout the life-cycle of the Air Force KC-X...

  20. Automated Aerial Refueling Presentation to 2007 ARSAG Conference (Preprint)

    Science.gov (United States)

    2007-04-01

    this technology allows manned or unmanned platforms to fly formation in IFR conditions. 3 3Approved for public release; distribution is unlimited...conducted in conjunction with the DARPA TTNT China Lake test It was determine that TTNT needed slight modifications which have been incorporated. Station

  1. A Virtual Reality Framework to Optimize Design, Operation and Refueling of GEN-IV Reactors

    International Nuclear Information System (INIS)

    Rizwan-uddin; Nick Karancevic; Stefano Markidis; Joel Dixon; Cheng Luo; Jared Reynolds

    2008-01-01

    Many GEN-IV candidate designs are currently under investigation. Technical issues related to material, safety and economics are being addressed at research laboratories, industry and in academia. After safety, economic feasibility is likely to be the most important criterion in the success of GEN-IV design(s). Lessons learned from the designers and operators of GEN-II (and GEN-III) reactors must play a vital role in achieving both safety and economic feasibility goals

  2. A Virtual Reality Framework to Optimize Design, Operation and Refueling of GEN-IV Reactors.

    Energy Technology Data Exchange (ETDEWEB)

    Rizwan-uddin; Nick Karancevic; Stefano Markidis; Joel Dixon; Cheng Luo; Jared Reynolds

    2008-04-23

    many GEN-IV candidate designs are currently under investigation. Technical issues related to material, safety and economics are being addressed at research laboratories, industry and in academia. After safety, economic feasibility is likely to be the most important crterion in the success of GEN-IV design(s). Lessons learned from the designers and operators of GEN-II (and GEN-III) reactors must play a vital role in achieving both safety and economic feasibility goals.

  3. 40 CFR 86.1821-01 - Evaporative/refueling family determination.

    Science.gov (United States)

    2010-07-01

    ... family determination. (a) The gasoline-, methanol-, liquefied petroleum gas-, and natural gas-fueled... control strategy). (8) Vapor hose material. (9) Fuel tank material. (c) Where vehicles are of a type which...

  4. Optimization of refueling loading pattern of uranium zirconium hydride research reactor

    International Nuclear Information System (INIS)

    Chen Wei; Xie Zhongsheng; Chen Da

    1999-01-01

    The orthogonal design method is used in the optimization of in-core fuel management. A code package of in-core fuel management in hexagonal geometry HEX-ORTH is developed. The loading pattern after the end of 3 cycle of Xi'an Pulsed Reactor is optimized using the HEX-ORTH. The optimistic loading pattern of the core are obtained as the objective function is Max(k eff BOC )

  5. INFLAMMABLE ABILITY ELECTRIC DISCHARGE OF THE STATIC ELECTRICITY in REFUELLING AIRcraft

    Directory of Open Access Journals (Sweden)

    N. E. Syrojedov

    2014-01-01

    Full Text Available The article deals with the improvement of the methodical base and the results of the research in the field of inflammable ability of static electricity discharges in the environment of aviation fuel stream.

  6. Next Generation Tanker: Optimizing Air Refueling Capabilities in 2030 with a Divested KC-10 Fleet

    Science.gov (United States)

    2015-06-19

    Alfred North Whitehead This chapter analyzes the linear program results, development and procurement costs of the three proposal aircraft, and...shrinking Defense Budget. 31 Bibliography Braybrook, R. (2011). Fighter Thirst Quenchers. Armada International, 35(3), 30. Chandler , S

  7. The Maharaja’s New AVTAAR: Air-Refuelling Strategy for the Indian Air Force

    Science.gov (United States)

    2013-06-01

    mapping the country, patrolling the forests to prevent forest fires , carrying the mail, eliminating insect pests from cotton, fruit trees and other...relationship between the government and the nation’s air carriers.31 Sections of this report catered to emergency needs of the DOD, assessed tariff ...participation due to issues of insurance in a war zone, and the potential loss of market share (especially for large carriers).41 Also, a few CRAF aircrew

  8. Application of railgun principle to high-velocity hydrogen pellet injection for magnetic fusion reactor refueling

    International Nuclear Information System (INIS)

    Kim, K.

    1991-08-01

    This report contains three documents describing the progress made by the University of Illinois electromagnetic railgun program sponsored by the Office of Fusion Energy of the United States Department of Energy during the period from July 16, 1990 to August 16, 1991. The first document contains a brief summary of the tasks initiated, continued, or completed, the status of major tasks, and the research effort distribution, estimated and actual, during the period. The second document contains a description of the work performed on time resolved laser interferometric density measurement of the railgun plasma-arc armature. The third document is an account of research on the spectroscopic measurement of the electron density and temperature of the railgun plasma arc

  9. Comparison of conventional vs. modular hydrogen refueling stations and on-site production vs. delivery.

    Energy Technology Data Exchange (ETDEWEB)

    Hecht, Ethan S. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Pratt, Joseph William [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

    2017-03-01

    To meet the needs of public and private stakeholders involved in the development, construction, and operation of hydrogen fueling stations needed to support the widespread roll-out of hydrogen fuel cell electric vehicles, this work presents publicly available station templates and analyses. These ‘Reference Stations’ help reduce the cost and speed the deployment of hydrogen stations by providing a common baseline with which to start a design, enable quick assessment of potential sites for a hydrogen station, identify contributors to poor economics, and suggest areas of research. This work presents layouts, bills of materials, piping and instrumentation diagrams, and detailed analyses of five new station designs. In the near term, delivered hydrogen results in a lower cost of hydrogen compared to on-site production via steam methane reforming or electrolysis, although the on-site production methods have other advantages. Modular station concepts including on-site production can reduce lot sizes from conventional assemble-on-site stations.

  10. Recycling studies in the ASDEX divertor with pellet or gas puff refuelling

    International Nuclear Information System (INIS)

    Haas, G.; Kaufmann, M.; Lang, R.S.; Mertens, V.; Niedermeyer, H.; Sandmann, W.; Becker, G.; Bosch, H.S.; Brocken, H.; Buechl, K.; Eberhagen, A.; Fussmann, G.; Gehre, O.; Gernhardt, J.; Gierke, G.; Glock, E.; Gruber, O.; Hofmann, J.; Janeschitz, G.; Karger, F.; Keilhacker, M.; Klueber, O.; Kornherr, M.; Lackner, K.; Lenoci, M.; Lisitano, G.; Mast, F.; Mayer, H.M.; McCormick, K.; Meisel, D.; Mueller, E.R.; Murmann, H.; Neuhauser, J.; Poschenrieder, W.; Rapp, H.; Riedler, H.; Roehr, H.; Roth, J.; Schneider, F.; Setzensack, C.; Siller, G.; Smeulders, P.; Soeldner, F.X.; Speth, E.; Steuer, K.H.; Vollmer, O.; Wagner, F.; Zasche, D.; Izvozchikov, A.; Ryter, F.; Tsois, N.; Ugniewski, S.

    1987-01-01

    Discharges fuelled by stationary pellet injection (PI), gas puffing (GP) or a combination of the two methods are compared with respect to recycling in the divertor and particle confinement. Fuelling by PI yields much better global particle confinement than by GP. This has been found for both low and high recycling. In the low-recycling case this improvement is due to the deeper particle deposition for PI than for GP since the transport in the inner plasma is not reduced. For high recycling the improvement results from both the deeper deposition and a reduction in the transport. The best global particle confinement was found for phases with low or no GP. This, however, can be reached for short times only. Since with PI alone it is impossible to keep the recycling on a high level, GP is unavoidable for sustaining the favourable high-recycling condition. (orig.)

  11. Refuelling design and core calculations at NPP Paks: codes and methods

    International Nuclear Information System (INIS)

    Pos, I.; Nemes, I.; Javor, E.; Korpas, L.; Szecsenyi, Z.; Patai-Szabo, S.

    2001-01-01

    This article gives a brief review of the computer codes used in the fuel management practice at NPP Paks. The code package consist of the HELIOS neutron and gamma transport code for preparation of few-group cross section library, the CERBER code to determine the optimal core loading patterns and the C-PORCA code for detailed reactor physical analysis of different reactor states. The last two programs have been developed at the NPP Paks. HELIOS gives sturdy basis for our neutron physical calculation, CERBER and C-PORCA programs have been enhanced in great extent for last years. Methods and models have become more detailed and accurate as regards the calculated parameters and space resolution. Introduction of a more advanced data handling algorithm arbitrary move of fuel assemblies can be followed either in the reactor core or storage pool. The new interactive WINDOWS applications allow easier and more reliable use of codes. All these computer code developments made possible to handle and calculate new kind of fuels as profiled Russian and BNFL fuel with burnable poison or to support the reliable reuse of fuel assemblies stored in the storage pool. To extend thermo-hydraulic capability, with KFKI contribution the COBRA code will also be coupled to the system (Authors)

  12. Genetic algorithms used for PWRs refuel management automatic optimization: a new modelling

    International Nuclear Information System (INIS)

    Chapot, Jorge Luiz C.; Schirru, Roberto; Silva, Fernando Carvalho da

    1996-01-01

    A Genetic Algorithms-based system, linking the computer codes GENESIS 5.0 and ANC through the interface ALGER, has been developed aiming the PWRs fuel management optimization. An innovative codification, the Lists Model, has been incorporated to the genetic system, which avoids the use of variants of the standard crossover operator and generates only valid loading patterns in the core. The GENESIS/ALGER/ANC system has been successfully tested in an optimization study for Angra-1 second cycle. (author)

  13. Air Refueling Operations in the North Pacific: Is There a More Efficient Method?

    National Research Council Canada - National Science Library

    Rauenhorst, Michael

    1998-01-01

    ... in new mission areas and optimizing the reverse associate unit. The best location to attempt either a KC-135 reverse associate unit or a non-traditional Air National Guard KC-135 squadron might be in the North Pacific Theater...

  14. Pellets for fusion reactor refueling. Annual progress report, January 31, 1977--January 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    Progress during the past year has occurred in the following areas. A pellet generator for larger pellets is currently under construction. Alternate pellet generation techniques are under investigation. Progress has been made on the pellet selection and acceleration scheme for the large pellet generator. Work has begun on ablation acceleration for accelerating pellets to very high velocities. In the area of pellet-plasma interactions work has been completed on a transonic flow model and papers have been published dealing with both experimental and theoretical aspects of the problem.

  15. Electromagnetism Mechanism for Enhancing the Refueling Cycle Length of a WWER-1000

    Directory of Open Access Journals (Sweden)

    Navid Poursalehi

    2017-02-01

    Full Text Available Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM, is applied to the fuel arrangement design of the Bushehr WWER-1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation. The first results of the prepared package, along with the cycle for the original pattern of Bushehr WWER-1000, are compared and verified according to the Final Safety Analysis Report and then the results of exploited EM linked with Purdue Advanced Reactor Core Simulator (PARCS and Winfrith Improved Multigroup Scheme (WIMS codes are reported for the loading pattern optimization. Totally, the numerical results of our loading pattern optimization indicate the power of the EM for this problem and also show the effective improvement of desired parameters for the gained semi-optimized core pattern in comparison to the designer scheme.

  16. Electromagnetism mechanism for enhancing the refueling cycle length of a WWER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Poursalehi, Navid; Nejati-Zadeh, Mostafa; Minuchehr, Abdolhamid [Dept. of Nuclear Engineering, Shahid Beheshti University, Tehran (Iran, Islamic Republic of)

    2017-02-15

    Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM), is applied to the fuel arrangement design of the Bushehr WWER-1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation. The first results of the prepared package, along with the cycle for the original pattern of Bushehr WWER-1000, are compared and verified according to the Final Safety Analysis Report and then the results of exploited EM linked with Purdue Advanced Reactor Core Simulator (PARCS) and Winfrith Improved Multigroup Scheme (WIMS) codes are reported for the loading pattern optimization. Totally, the numerical results of our loading pattern optimization indicate the power of the EM for this problem and also show the effective improvement of desired parameters for the gained semi-optimized core pattern in comparison to the designer scheme.

  17. Pragmatic Divestment of KC-135 Navigators in the Special Operations Air Refueling Mission

    Science.gov (United States)

    2015-03-26

    publicly expressed opinions, and the bandwagon effect of majority opinion. This technique replaces direct debate by a carefully designed program of... effective , comprehensive solution. Ultimately, the panel of experts arrived at conclusions supporting the hypothesis that navigator divestment and SOAR...manpower, personnel, and training effects after navigators are phased out

  18. Basing Strategies for Air Refueling Forces in Anti-access/Area-Denial Environments

    Science.gov (United States)

    2015-09-01

    likely, increase manpower allocations to provide specialist technician coverage at all locations. Connecting subunits by air or surface lift could re...at disaggregated bases also may be overwhelmed by local challenges ranging from base security breaches and supply shortages to the presence of...supported units offers some opportunity to protect tanker forces. But the requirement to establish supply warehouses , access agreements, and the like

  19. New concepts for small power reactors without on-site refuelling for non-proliferation

    International Nuclear Information System (INIS)

    Brown, N.W.; Hasberger, J.A.

    2000-01-01

    The report discusses the preliminary requirements and a technical approach for developing small reactors and the rationale for selecting them. It then discusses the four nuclear system technologies and how they might proceed to meet the requirements. Brief discussions are provided on the approaches to stimulating the appropriate international and industrial participation necessary to finance development of a design with improved proliferation resistance that is useful to the developing countries. (author)

  20. Becoming part of the story! Refueling the interest in visualization strategies for reading comprehension

    NARCIS (Netherlands)

    de Koning, B.B.; van der Schoot, M.

    2013-01-01

    Visualizing the events described in a text is crucial for constructing a rich and coherent visuospatial mental representation (i.e., situation model) of the text. According to current reading comprehension theories, the construction of such a situation model likely involves all sensory modalities.

  1. On the boundary conditions and validity of the neutral shielding model of a refuelling pellet

    International Nuclear Information System (INIS)

    Chang, C.T.

    1982-02-01

    By comparing the ablation time of a hydrogen pellet in a tokamak discharge with the time required for the sublimation process, the vaporization of the pellet is shown to be a dynamic phase transition - i.e. the transport of heat is due to the propagation of an evaporation front. Based on this finding, an alternative boundary condition, consistent with the energy conservation law, is formulated. Computational results utilizing the new boundary condition indicate that the ablatant near the pellet surface is hotter and less dense compared with the results which make use of the previous condition of the vanishing flux. The discrepancy between the two solutions becomes less significant once the ablatant reaches the sonic radius. The scaling law of the pellet ablation rate is unaffected by this change of boundary condition. The present analysis shows that the validity of the neutral shielding model is based mainly on the existence of a thin envelope around the pellet where strong energy absorption occurs and is insensitive to the actual vaporization process occuring at the pellet surface. (Auth.)

  2. NREL-Developed CUBE Helps Solve Army's Refueling Challenge | News | NREL

    Science.gov (United States)

    (such as solar panels, batteries, and generators) into usable electricity-and swiftly switches between turbine, roll-out solar panels, batteries, and small diesel generators. When the Army requested additional in it. You connect the solar panels to it. You connect the battery to it. You connect the generator

  3. Pellets for fusion reactor refueling. Annual progress report, January 31, 1977--January 31, 1978

    International Nuclear Information System (INIS)

    1978-01-01

    Progress during the past year has occurred in the following areas. A pellet generator for larger pellets is currently under construction. Alternate pellet generation techniques are under investigation. Progress has been made on the pellet selection and acceleration scheme for the large pellet generator. Work has begun on ablation acceleration for accelerating pellets to very high velocities. In the area of pellet-plasma interactions work has been completed on a transonic flow model and papers have been published dealing with both experimental and theoretical aspects of the problem

  4. The process of NPP refuelling outage analysis and follow-up

    International Nuclear Information System (INIS)

    Nemec, T.; Savli, S.; Cernilogar Radez, M.; Persic, A.; Pecek, V.; Stritar, A.

    2007-01-01

    Following the outages in 2004 and 2006, the Slovenian Nuclear Safety Administration (SNSA) has started with the practice of independent outage analysis in a form of an internal report. It includes a comparison of performed activities against the planned time schedule of activities, evaluation of design modifications implementation and analysis of significant events. The main result of the outage analysis is a list of recommendations and some open issues that have been identified. These findings are the basis for development of an action plan for SNSA activities until the next outage, aimed at eliminating deficiencies found out during the outage and further improving outage activities. The established system of outage supervision together with the final analysis and long term action plan represents an effective continuous safety supervision process, by which the regulatory body independently contributes to the higher level of safety culture both at the licensee and among its own staff. (author)

  5. Practice of the rotation of assemblies during refuelling in NPP of Paks

    International Nuclear Information System (INIS)

    Szecsenyi, Z.

    1998-01-01

    Few years ago it turned out that two kk distributions could differ from each other if the kk is calculated using pin-wise burn-up distribution and the pin-wise burn-up distribution is very slanted or using averaged burn-up distribution. In that case when the former manner calculated value of kkmax is higher then the other one, the value of kkmax can be decreased with the rotation of the assembly. As a consequence of the development of computer technique an opportunity presents itself for the practical application of pin-wise burn-up calculation. At the outset the pin-wise burn-up calculation was made for that assembly, where the reactor-physics parameters were near the safety values. Nowadays the further development of the hardware and software devices present opportunity for the full-scope following of the pin-wise burn-up, in all assemblies. In this paper is presented a short historical review of the above mentioned events, practical adaption of the pin-wise burn-up following and display of some used reactor-physics codes.(Author)

  6. Scaling and parametric studies of condensation oscillation in an in-containment refueling water storage tank

    International Nuclear Information System (INIS)

    Lee, Jun Hyung; No, Hee Cheon

    2001-01-01

    The purpose of this paper is to study the condensation oscillation phenomena by steam-jetting into subcooled water through a sparger, implementing a scaling methodology and the similarity correlation between the test facility and model prototype. In additon, the results of this study can provide suitable guidelines for sparger design utilized in the IRWST for the Advanced Passive Reactor 1400 (APR 1400). To corroborate the scaling methodology, various experimental tests were conducted. The scaling-related parameters experimentally considered were water temperatures, mass flux, discharge system volumes, tank sizes, source pressure, steam-jetting directions, and numbers of sparger discharge holes. To preserve the scaling similarity, the thickness of the minimum water volume created by the boundary layer that encloses the steam cavity was found to be equal to the maximum length of the steam cavity formed. Four key scaling parameters were identified and empirically correlated with the maximum amplitude of pressure oscillation. They are as follows: Volume of the steam cavity, flow restriction coefficient, discharge hole area, and density ratio of steam to water. Variations of the oscillation amplitude were small when steam-jetting directions were altered. The concept of a reduction factor was introduced for estimating the oscillation amplitude of the multi-hole sparger with test data from a single-hole sparger

  7. Hydrogen Car Cartridges: A New Strategy for Hydrogen Storage, Delivering and Refueling

    Energy Technology Data Exchange (ETDEWEB)

    Prosini, Pier Paolo

    2007-07-01

    The purpose of the project is to introduce a sustainable model in the automotive field, guarantying the Kyoto agreements. The aim of the project is to develop an innovative hydrogen tank able to power an hydrogen fuel cell car with the same performance of liquid fuelled cars. Most of the system performance are expected to satisfy the Department of Energy (DOE) goals for 2015. The hydrogen releasing system is based on solid NaBH4 which is hydrolyzed with water or steam to obtain hydrogen. Sodium borate is obtained as by-product and it has to be recycled. Pure and humidified hydrogen, ready to be utilized in a fuel cell, is obtained by a simple and sure way. Hydrogen is produced only when it is requested and therefore there is never pressurized hydrogen or hydrogen overproduction The system works at atmospheric pressure avoiding the problems related to handling and storing pressurized gas. The car fuelling could be performed in area like the present service stations. The used cartridges can be removed and substituted by new cartridges. Contemporarily a water tank should be refilled. To improve the total energetic yield it was also proposed a NaBH4 regeneration process directly starting from the products of hydrolysis. (auth)

  8. The sugar oxidation cascade: aerial refueling in hummingbirds and nectar bats.

    Science.gov (United States)

    Suarez, Raul K; Herrera M, L Gerardo; Welch, Kenneth C

    2011-01-15

    Most hummingbirds and some species of nectar bats hover while feeding on floral nectar. While doing so, they achieve some of the highest mass-specific V(O(2)) values among vertebrates. This is made possible by enhanced functional capacities of various elements of the 'O(2) transport cascade', the pathway of O(2) from the external environment to muscle mitochondria. Fasted hummingbirds and nectar bats fly with respiratory quotients (RQs; V(CO(2))/V(O(2))) of ~0.7, indicating that fat fuels flight in the fasted state. During repeated hover-feeding on dietary sugar, RQ values progressively climb to ~1.0, indicating a shift from fat to carbohydrate oxidation. Stable carbon isotope experiments reveal that recently ingested sugar directly fuels ~80 and 95% of energy metabolism in hover-feeding nectar bats and hummingbirds, respectively. We name the pathway of carbon flux from flowers, through digestive and cardiovascular systems, muscle membranes and into mitochondria the 'sugar oxidation cascade'. O(2) and sugar oxidation cascades operate in parallel and converge in muscle mitochondria. Foraging behavior that favours the oxidation of dietary sugar avoids the inefficiency of synthesizing fat from sugar and breaking down fat to fuel foraging. Sugar oxidation yields a higher P/O ratio (ATP made per O atom consumed) than fat oxidation, thus requiring lower hovering V(O(2)) per unit mass. We propose that dietary sugar is a premium fuel for flight in nectarivorous, flying animals.

  9. Precision Relative Positioning for Automated Aerial Refueling from a Stereo Imaging System

    Science.gov (United States)

    2015-03-01

    approaching the tanker. The box (left) represents the camera system housing and contains the points from which the imagery was rendered. Each simulation data...Proceedings. IEEE Workshop on, pages 59–68. IEEE, 1999. 64 29. B. W. Parkinson and P. K. Enge. Differential gps. Progress in Astronautics and Aeronautics

  10. 76 FR 41731 - Air Quality: Widespread Use for Onboard Refueling Vapor Recovery and Stage II Waiver

    Science.gov (United States)

    2011-07-15

    ... forced out of the tank as the tank fills with liquid gasoline. Where air pollution control technology is... this action include states (typically state air pollution control agencies) and, in some cases, local governments that develop air pollution control rules that apply to areas classified as ``Serious,'' ``Severe...

  11. 77 FR 28772 - Air Quality: Widespread Use for Onboard Refueling Vapor Recovery and Stage II Waiver

    Science.gov (United States)

    2012-05-16

    ... fills with liquid gasoline. Where air pollution control technology is not used, these vapors are emitted... states (typically state air pollution control agencies) and, in some cases, local governments that develop air pollution control rules that apply to areas classified as Serious and above for nonattainment...

  12. Air Force Air Refueling: The KC-X Aircraft Acquisition Program

    National Research Council Canada - National Science Library

    Bolkcom, Christopher; Knight, William

    2008-01-01

    .... The program is expected to cost approximately $35 billion. Both Boeing and a consortium consisting of Northrop Grumman and European Aeronautic Defence and Space Company (EADS) competed for KC-X...

  13. Application of railgun principle to high-velocity hydrogen pellet injection for magnetic fusion reactor refueling. Technical progress report

    International Nuclear Information System (INIS)

    Kim, K.K.

    1986-01-01

    Using a tungsten-needle arc initiator in conjunction with Paschen curves characteristics hydrogen pellets have been accelerated with a two-stage electromagnetic railgun system. This scheme produced velocities on the order of 1.6 km/s. The effects on performance of the bore size have been studied. Questions of pretriggering, misfiring, plasma-arc stalling, railgun geometry, and railgun currents have been addressed. 1 tab

  14. Running on Empty: The Development of Helicopter Aerial Refueling and Implications for Future USAF Combat Rescue Capabilities

    National Research Council Canada - National Science Library

    Colburn, Tracy

    1997-01-01

    .... The declining defense budget means painful force structure decisions lie ahead. Even as funds are drying up, the armed forces are being called upon to execute contingencies in places such as Haiti, Somalia, Liberia, and Bosnia...

  15. Modernizing the U.S. Aircraft Carrier Fleet: Accelerating CVN 21 Production versus Mid-Life Refueling

    National Research Council Canada - National Science Library

    Schank, John; Smith, Giles; Alkire, Brien; Arena, Mark V; Birkler, John; Chiesa, James; Keating, Edward; Schmidt, Lara

    2005-01-01

    .... This class of carriers will use the same basic hull form as the current Nimitz class, but will include a substantial redesign of the interior of the ship for improved weapons handling and stores management functions...

  16. Food, feeding, and refuelling of Red Knots during northward migration at San Antonio Oeste, Rio Negro, Argentina

    NARCIS (Netherlands)

    Gonzalez, PM; Piersma, T; Verkuil, Y; González, Patricia M.

    1996-01-01

    We studied the food and feeding ecology of Red Knots Calidris canutus rufa on an area of rocky flat, or restinga, near San Antonio Oeste in the northwest of Golfo San Matias, Provincia de Rio Negro, Argentina in March 1992. These Red Knots are on their way north, from ''wintering'' areas in Tierra

  17. Application of railgun principle to high-velocity hydrogen pellet injection for magnetic fusion reactor refueling: Technical progress report

    International Nuclear Information System (INIS)

    Kim, K.

    1986-01-01

    A detailed experimental study successfully demonstrates the acceleration of frozen hydrogen pellets by means of a fuseless two-stage electromagnetic railgun system. This system consists of a pneumatic hydrogen pellet injector, which freezes and pneumatically pre-accelerates (with high-pressure helium as the propellant gas) cylindrical 1.6-mm-dia by 2.15-mm-long hydrogen pellets, and a 60-cm-long, 1.6-mm-dia circular-bore electromagnetic railgun. The pellet is introduced into the railgun by means of a coupling piece, and a plasma-arc armature is created from the propellant gas by means of a very unique, fuseless, arc-initiation scheme. Railgun-accelerated hydrogen pellet velocities in excess of 1.6 km/s are achieved from pneumatically accelerated injection velocities of 800 m/s. Streak-camera and current-probe data show that the plasma-arc armature moves at a velocity proportional to the railgun current, I. Insight to this I-dependence is gained through the use of streak photography and current probes for varying bore geometries and gas pressures

  18. Role of advanced refuelling and heating on edge Reynolds stress-induced poloidal flow in HL-1M

    International Nuclear Information System (INIS)

    Hong Wenyu; Wang Enyao; Li Qiang; Cao Jianyong; Yan Longwen

    2002-01-01

    The radial profile of electrostatic Reynolds stress, plasma poloidal rotations, radial and poloidal electric fields have been measured in the plasma boundary region of the HL-1M tokamak using a multi-array of Mach/Langmuir probes. In the experiments of ohmic discharge, lower hybrid current drive, supersonic molecular beam injection (SMBI) and multi-shot pellet injection, the correlation between the Reynolds stress and poloidal flow in the edge plasma is presented. The radial profile changes of the Reynolds stress and poloidal flow velocity V pol with lower hybrid wave injection power and SMBI injection are obtained. The results indicate that the sheared poloidal flow can be generated in tokamak plasma due to the radially varying Reynolds stress

  19. Bewick's Swans refuelling on pondweed tubers in the Dvina Bay (White Sea) during their spring migration: first come, first served

    NARCIS (Netherlands)

    Nolet, B.A.; Drent, R.H.

    1998-01-01

    Current models of bird migration consider the optimal decision making of individuals irrespective of the behaviour of conspecifics. We observed the foraging behaviour of Bewick's Swans Cygnus columbianus during their stop-over in the Dvina Bay in the White Sea in spring 1995 and 1996. Here the swans

  20. Bewick's Swans refuelling on pondweed tubers in the Dvina Bay (White Sea) during their spring migration : first come, first served

    NARCIS (Netherlands)

    Nolet, BA; Drent, RH

    1998-01-01

    Current models of bird migration consider the optimal decision making of individuals irrespective of the behaviour of conspecifics. We observed the foraging behaviour of Bewick's Swans Cygnus columbianus during their stop-over in the Dvina Bay in the White Sea in spring 1995 and 1996. Here the swans

  1. A two-stage pneumatic repeating pellet injector for refueling magnetically confined plasmas in long-pulse fusion experiments

    International Nuclear Information System (INIS)

    Frattolillo, A.; Migliori, S.; Scaramuzzi, F.; Capobianchi, M.; Domma, C.; Ronci, G.

    1995-01-01

    An experiment to demonstrate the feasibility of a repetitive pneumatic pellet injector at 1 Hz in the velocity range of 2 to 3 knVs was carried out in a collaboration between Oak Ridge National Laboratory and ENEA Frascati, in the context of a cooperative agreement between the US Department of Energy and EURATOM-ENEA Association. The third round of this experiment was completed in May 1995. Both the operation and performance of the equipment were improved, and the original objectives of the collaboration have been met. The facility was also briefly operated with neon pellets to explore the potential for producing fast ''killer'' pellets for disruption amelioration applications. Speeds of 1.7 km/s were achieved using a piston mass of 43 g. Higher speeds should be achievable with a system specifically designed for neon or other higher Z gases. Finally, tests were performed with thin boron carbide coatings (2 μm) on the Ergal pistons. The test results were encouraging because piston friction was reduced was the piston wear

  2. In core fuel management optimization by varying the equilibrium cycle average flux shape for batch refuelled reactors

    International Nuclear Information System (INIS)

    Jong, A.J. de.

    1992-12-01

    We suggest a method to overcome this problem of optimization by varying reloading patterns by characterizing each particular reloading pattern by a set of intermediate parameters that are numbers. Plots of the objective function versus the intermediate parameters can be made. When the intermediate parameters represent the reloading patterns in a unique way, the optimum of the objective function can be found by interpolation within such plots and we can find the optimal reloading pattern in terms of intermediate parameters. These have to be transformed backwards to find an optimal reloading pattern. The intermediate parameters are closely related to the time averaged neutron flux shape in the core during an equilibrium cycle. This flux shape is characterized by a set of ratios of the space averaged fluxes in the fuel zones and the space averaged flux in the zone with the fresh fuel elements. An advantage of this choice of intermediate parameters is that it permits analytical calculation of equilibrium cycle fuel densities in the fuel zones for any applied reloading patten characterized by a set of equilibrium cycle average flux ratios and thus, provides analytical calculations of fuel management objective functions. The method is checked for the burnup of one fissile nuclide in a reactor core with the geometry of the PWR at Borssele. For simplicity, neither the conversion of fuel, nor the buildup of fission products were taken into account in this study. Since these phenomena can also be described by the equilibrium cycle average flux ratios, it is likely that this method can be extended to a more realistic method for global in core fuel management optimization. (orig./GL)

  3. Food, the Nutritional Product that Fuels the Passing of Time: How Time and Nutrition Transformed Eating into Refuelling

    OpenAIRE

    Cawley, Diarmuid

    2014-01-01

    Food is in front of us everywhere we go; marketed and ready to eat. The easier it is to consume food ‘on the go’ the more socially accepted it becomes. The private elements of food consumption have unwittingly become the public elements of food consumption, sometimes excruciatingly public, with food reconnaissance for most of us now a redundant act. The exogenic nature of passing time and our ever increasing need to partake in complex travel systems to and from our daily destinations has enga...

  4. Rapid population decline in red knots : fitness consequences of decreased refuelling rates and late arrival in Delaware Bay

    NARCIS (Netherlands)

    Baker, AJ; Gonzalez, PM; Piersma, T; Niles, LJ; do Nascimento, IDS; Atkinson, PW; Clark, NA; Minton, CDT; Peck, MK; Aarts, G

    2004-01-01

    Most populations of migrant shorebirds around the world are in serious decline, suggesting that vital condition-dependent rates such as fecundity and annual survival are being affected globally. A striking example is the red knot (Calidris canutus rufa) population wintering in Tierra del Fuego,

  5. User manual of Visual Balan V. 1.0 Interactive code for water balances and refueling estimation

    International Nuclear Information System (INIS)

    Samper, J.; Huguet, L.; Ares, J.; Garcia, M. A.

    1999-01-01

    This document contains the Users Manual of Visual Balan V1.0, an updated version of Visual Balan V0.0 (Samper et al., 1997). Visual Balan V1.0 performs daily water balances in the soil, the unsaturated zone and the aquifer in a user-friendly environment which facilitates both the input data process and the postprocessing of results. The main inputs of the balance are rainfall and irrigation while the outputs are surface runoff, evapotranspiration, interception, inter flow and groundwater flow. The code evaluates all these components in a sequential manner by starting with rainfall and irrigation, which must be provided by the user, and continuing with interception, surface runoff, evapotranspiration, and potential recharge (water flux crossing the bottom of the soil). This potential recharge is the input to the unsaturated zone where water can flow horizontally as subsurface flow (inter flow) or vertically as percolation into the aquifer. (Author)

  6. Parametric and scaling studies of condensation oscillation in subcooled water of the in-containment refueling water storage tank

    International Nuclear Information System (INIS)

    Lee, Jun Hyung; No, Hee Cheon

    1999-01-01

    Condensation oscillation by jetting the steam into subcooled water through spargers is studied. To provide a suitable guideline for oscillation phenomena in the IRWST of the next generation reactor, scaling methodology is introduced. Through scaling methodology and subsequent tests, it shows that the volume of steam cavity determines the dynamic characteristics of condensation oscillation. The second-order linear differential equation for frequency analysis is derived and its results are compared with those from the test data. Two types of condensation phenomena exist according to steam flow rates. At subsonic jet, condensation interface becomes irregular in shape and upper system volumes affect the dynamic characteristics of condensation oscillation. At sonic jet, a regular steam cavity forms at the exit of discharge holes. Parametric effects and subsequent dynamic responses of the pool tank are investigated through experiments in applicable test ranges. When the temperature of pool water becomes lower, the amplitude becomes larger. Critical parameters are derived from the scaling methodology and are system volume, cavity volume, discharge hole area, and density ration. It is found that system friction factors affect frequency components of condensation oscillation. Oscillations of a steam cavity occur mainly on the face of the axial direction and pressure amplitudes become larger than that of the lateral direction

  7. LARA. Localization of an automatized refueling machine by acoustical sounding in breeder reactors - implementation of artificial intelligence techniques

    International Nuclear Information System (INIS)

    Lhuillier, C.; Malvache, P.

    1987-01-01

    The automatic control of the machine which handles the nuclear subassemblies in fast neutron reactors requires autonomous perception and decision tools. An acoustical device allows the machine to position in the work area. Artificial intelligence techniques are implemented to interpret the data: pattern recognition, scene analysis. The localization process is managed by an expert system. 6 refs.; 8 figs

  8. Environmental Assessment: Proposed Construction, Demolition, and Other Actions at the 126th Air Refueling Wing Illinois Air National Guard

    Science.gov (United States)

    2006-06-05

    FIFRA Federal Insecticide , Fungicide, and Rodenticide Act FONSI Finding of No Significant Impact FY fiscal year HAP High Accident Potential HAZMAT...approximately 30 to 40 percent open (Scott AFB 2005b). The understory of the Riparian Forest is relatively sparse; however, stinging nettle and white heath...waste laws and regulations. Federal Insecticide , Fungicide, and Rodenticide Act (FIFRA) of 1996 (7 USC 136 et seq.). FIFRA provides federal control

  9. Resolving piping analysis issues to minimize impact on installation activities during refueling outage at nuclear power plants

    International Nuclear Information System (INIS)

    Bhavnani, D.

    1996-01-01

    While it is required to maintain piping code compliance for all phases of installation activities during outages at a nuclear plant, it is equally essential to reduce challenges to the installation personnel on how plant modification work should be performed. Plant betterment activities that incorporate proposed design changes are continually implemented during the outages. Supporting analysis are performed to back these activities for operable systems. The goal is to reduce engineering and craft man-hours and minimize outage time. This paper outlines how plant modification process can be streamlined to facilitate construction teams to do their tasks that involve safety related piping. In this manner, installation can proceed by minimizing on the spot analytical effort and reduce downtime to support the proposed modifications. Examples are provided that permit performance of installation work in any sequence. Piping and hangers including the branch lines are prequalified and determined operable. The system is up front analyzed for all possible scenarios. The modification instructions in the work packages is flexible enough to permit any possible installation sequence. The benefit to this approach is large enough in the sense that valuable outage time is not extended and on site analytical work is not required

  10. Build-up of Red Blood Cells in Refuelling Bar-Tailed Godwits in Relation to Individual Migratory Quality

    NARCIS (Netherlands)

    Piersma, Theunis; Everaarts, Jan M.; Jukema, Joop

    1996-01-01

    We examined hemoglobin concentration, hematocrit and mean cell hemoglobin concentration (MCHbC) in Bar-tailed Godwits Limosa lapponica during the latter half of their staging period in May in the Wadden Sea of The Netherlands. Here they recover from a 4,000-5,000 km long flight from West African

  11. Survey of Current US Army POL Doctrine, Procedures, Personnel, and Equipment for the Supply and Inland Distribution of Bulk POL

    Science.gov (United States)

    1985-10-01

    Refueling Under Armor ......................... 34 Page i ,t .J APPENDICES A. POL Unit Missions and Capabilities ....................... A-I B. Roster...refueling Open versus closed port refueling Requirement for Refueling Under Armor Robotic refueler V % Page 34 S.< ’p. ". APPgeDI A-"" • " ’ ’ POL " it

  12. Physical models and codes for prediction of activity release from defective fuel rods under operation conditions and in leakage tests during refuelling

    International Nuclear Information System (INIS)

    Likhanskii, V.; Evdokimov, I.; Khoruzhii, O.; Sorokin, A.; Novikov, V.

    2003-01-01

    It is appropriate to use the dependences, based on physical models, in the design-analytical codes for improving of reliability of defective fuel rod detection and for determination of defect characteristics by activity measuring in the primary coolant. In the paper the results on development of some physical models and integral mechanistic codes, assigned for prediction of defective fuel rod behaviour are presented. The analysis of mass transfer and mass exchange between fuel rod and coolant showed that the rates of these processes depends on many factors, such as coolant turbulent flow, pressure, effective hydraulic diameter of defect, fuel rod geometric parameters. The models, which describe these dependences, have been created. The models of thermomechanical fuel behaviour, stable gaseous FP release were modified and new computer code RTOP-CA was created thereupon for description of defective fuel rod behaviour and activity release into the primary coolant. The model of fuel oxidation in in-pile conditions, which includes radiolysis and RTOP-LT after validation of physical models are planned to be used for prediction of defective fuel rods behaviour

  13. Assessment of subcriticality during PWR-type reactor refueling; Evaluation de la sous-criticite lors des operations de chargement d'un reacteur nucleaire REP

    Energy Technology Data Exchange (ETDEWEB)

    Verdier, A

    2005-04-15

    During the core loading period of a PWR, any fuel assembly misplacements may significantly reduce the existing criticality margin. The Dampierre 4-18 event showed the present monitoring based on the variations of the outside-core detector counting rate cannot detect such misplacements. In order to circumvent that, a more detailed analysis of the available signal was done. We particularly focused on the neutronic noise analysis methods such as MSM (modified source multiplication), MSA (amplified source multiplication), Rossi-{alpha} and Feynman-{alpha} methods. The experimental part of our work was dedicated to the application of those methods to a research reactor. Finally, our results showed that those methods cannot be used with the present PWR instrumentation. Various detector positions were then studied using Monte Carlo calculations capable of following the neutron origin. Our results showed that the present technology does not allow us to use any solution based on neutron detection for monitoring core loading. (author)

  14. Site Investigation Report. 161st Air Refueling Group, Arizona National Guard, Sky Harbor International Airport and Papago Military Reservation, Phoenix, Arizona. Volume 1. Report, Tables and Figures

    Science.gov (United States)

    1992-11-01

    channel, floodplain, and alluvial fan environments derived from drainage areas of the Salt, Gila, Agua Fria, and Verde Rivers. Thickness of upper unit...groundwater media under consideration should be demonstrated to be potable and utilized as drinldng water, either currently or at some planncA future

  15. Comprehensive thermal-hydraulic and thermal-mechanical analysis of core and fuel rods for the safety validation of real refueling at the Kozloduy WWER-440

    Energy Technology Data Exchange (ETDEWEB)

    Stefanova, S; Panajotov, D; Ilieva, B; Vitkova, M; Simeonova, V; Passage, G; Manolova, M [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika

    1996-12-31

    Safety analysis aimed at determination of thermal-hydraulic and thermal-mechanical margins of core and fuel rods has been carried out using computer codes COBSOFM and PIN-micro. Thermal-hydraulic calculations for the part of the core with maximum heat flux during steady-state regime show that the coolant, cladding and fuel temperatures are within the design limits. A severe accident with reactor blackout has been simulated. It is found that at 95% probability level there is no boiling crisis anywhere in the core. The thermal-mechanical parameters of working assembly fuel rod with maximum load have been calculated. The assembly linear power reached a maximum of 25 kW/m during the second fuel cycle, the fuel temperature remaining well below 1000{sup o} C. As the fuel assembly with typical power history has enough safety margins, it was proposed to use it for one more cycle. 4 refs., 12 figs.

  16. Running-in strategies for the low-enriched 600 MW(e) D-HHT reactor. Part 1. Comparison of different on-load refuelling schemes

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, U

    1973-03-14

    This paper presents detailed burn-up calculations and fuel management strategies for the Dragon-HHT, D-HHT, reference core. The reference layout was chosen from the outcome of a design survey with the 1-D equilibrium fuel cycle code FLATTER. The decision was based on aspects of engineering and economics. The purpose of the investigation is to devise a suitable first core, follow the irradiation history of the fuel and the general behaviour of the reactor during the first core replacements until equilibrium operating conditions are reached. A detailed description of time dependant burn-up and spatial power production for specified reactivity limits is required. For this purpose the reactor code system VSOP was employed. Different combinations of the parameters are investigated and the influence on reactor operation and economics discussed. From the strategy analysis a reference fuel management scheme is chosen for the low enriched 600 MW(e) D-HHT reactor.

  17. Omega Air 707/F/A-18A-D Aerial Refueling Ground and Flight Test Evaluation and MA-3-1 Coupling Ground Test Evaluation

    National Research Council Canada - National Science Library

    Markowich, Brian

    2001-01-01

    Omega Air, Incorporated, a private organization that provides shipping and transportation services, contracted Marconi Flight Systems, Incorporated, to retrofit a Boeing 707 aircraft with an internal...

  18. High pressure thimble/guide tube seal fitting with built-in low pressure seal especially suitable for facilitated and more efficient nuclear reactor refueling service

    International Nuclear Information System (INIS)

    Bhatt, P.N.; Blaushield, R.M.

    1991-01-01

    This patent describes a HP/LP seal arrangement for an elongated guide tube and an elongated thimble disposed therein. The guide tube and thimble extending outwardly from the core of a nuclear reactor to a seal table where the guide tube is welded to the seal table to provide a high pressure seal relative thereto. It comprises: a tubular seal fitting disposed in alignment with the guide tube with the thimble extending therethrough on the low pressure side of the seal table; first high pressure sealing means coupling one end of the fitting to an end of the guide tube to prevent leakage from within the guide tube; inwardly facing thread means disposed adjacent the other and outer end of the seal fitting; a nut having an opening through which the thimble extends and further having outwardly facing threading in mating engagement with the fitting thread means; the fitting having a seal seat spaced longitudinally inwardly from the thread means and facing the fitting outer end and further disposed annularly about the inner surface of the fitting; deformable ring seal means; second releasable high pressure sealing means coupling the thimble to the outer end portion of the guide tube

  19. Machine learning techniques for the verification of refueling activities in CANDU-type nuclear power plants (NPPs) with direct applications in nuclear safeguards

    International Nuclear Information System (INIS)

    Budzinski, J.

    2006-06-01

    This dissertation deals with the problem of automated classification of the signals obtained from certain radiation monitoring systems, specifically from the Core Discharge Monitor (CDM) systems, that are successfully operated by the International Atomic Energy Agency (IAEA) at various CANDU-type nuclear power plants around the world. In order to significantly reduce the costly and error-prone manual evaluation of the large amounts of the collected CDM signals, a reliable and efficient algorithm for the automated data evaluation is necessary, which might ensure real-time performance with maximum of 0.01 % misclassification ratio. This thesis describes the research behind finding a successful prototype implementation of such automated analysis software. The finally adopted methodology assumes a nonstationary data-generating process that has a finite number of states or basic fueling activities, each of which can emit observable data patterns having particular stationary characteristics. To find out the underlying state sequences, a unified probabilistic approach known as the hidden Markov model (HMM) is used. Each possible fueling sequence is modeled by a distinct HMM having a left-right profile topology with explicit insert and delete states. Given an unknown fueling sequence, a dynamic programming algorithm akin to the Viterbi search is used to find the maximum likelihood state path through each model and eventually the overall best-scoring path is picked up as the recognition hypothesis. Machine learning techniques are applied to estimate the observation densities of the states, because the densities are not simply parameterizable. Unlike most present applications of continuous monitoring systems that rely on heuristic approaches to the recognition of possibly risky events, this research focuses on finding techniques that make optimal use of prior knowledge and computer simulation in the recognition task. Thus, a suitably modified, approximate n-best variant of the Viterbi algorithm is applied for the state sequence decoding, which allows for physical constraints derived from simulation models to be efficiently incorporated into the overall recognition scheme by appropriately rescoring the resulting n-best hypothesis lists. The physical constraints are derived from the local balance equation for precursors produced in fuel during discharge and the corresponding log-likelihood scores on the physical model are given by the negative chi-squared between the model predictions and data measurements. The proposed hybrid recognition algorithm is finally implemented in an automated fuel-handling verification system (AVER), the parameters of which are then optimized for maximum performance. This thesis also gives a dynamic, functional validation framework for such verification systems in nuclear safeguards, including the developed AVER system. The system's conclusions on random test data from both historical and synthesized data sets are compared against the relevant expert knowledge, and various metrics and risk measures are computed to judge the system's performance and reliability of its conclusions. The validation tests have shown that the developed verification system meets the desired competency requirements on its entire prespecified input domain of CANDU-6 data. Results on simulated data have also demonstrated the ability of the proposed system to detect radiation signatures corresponding to abnormal and rare events that normally do not appear in data. Throughout all the tests, AVER greatly outperformed an existing rudimentary verification system, consistently producing a reduction in the misclassification rate of about 170 %. The expected risk of undetected fuel discharge was estimated to be a hundred thousand times less than one significant quantity (SQ) of irradiated direct-use material (IDU) per unit per year, which is much below the acceptable limits and hence may be subject to no or only less intrusive safeguards. (author)

  20. Evolution of on-power refuelling system for 500 MWe PHWR based on experience from Rajasthan, Madras and Narora Atomic Power Stations

    International Nuclear Information System (INIS)

    Warrier, S.R.; Inder Jit; Sanatkumar, A.

    1991-01-01

    The on-power fuel handling system design at Rajasthan and Madras Atomic Power Stations (RAPS and MAPS) is essentially based on the design of the fuel handling system at Douglas Point Station (CANADA) Although, a number of improvements have been carried out in the fuel handling system of RAPS and MAPS at the component and sub-assembly level, some problems of repetitive nature like frequent deterioration in the performance of B-ram ball screw, leak detector solenoid valves etc., still exist. Further, there are certain limitations and drawbacks in the fuelling systems of these stations. For example, FM carriage design would not meet current seismic qualification standards. Also there are chances of fuel transfer room getting contaminated during movement of a failed fuel bundle. In order to obviate these deficiencies, a new concept has been worked out for the fuel handling system of Narora Atomic Power Station (NAPS) and accordingly, major changes have been made adopting a new layout. For example, FM head supporting arrangement has been changed to 'Suspension' type and a 'Linear-indexed' transfer magazine has been introduced in the fuel transfer system. Based on the experience gained from RAPS, MAPS and NAPS, design concept for 500 MWe fuel handling system has been evolved with further improvements especially in the layout. Also, a Calibration and Maintenance Facility for maintenance, testing calibration of FM head, sub-assemblies and components of fuel handling system has been introduced in the 500 MWe design. This paper discusses some of the experience gained from RAPS, MAPS and NAPS and also highlights the features of 500 MWe fuel handling system. (author)

  1. Safety performance comparation of MOX, nitride and metallic fuel based 25-100 MWe Pb-Bi cooled long life fast reactors without on-site refuelling

    International Nuclear Information System (INIS)

    Su'ud, Zaki

    2008-01-01

    In this paper the safety performance of 25-100 MWe Pb-Bi cooled long life fast reactors based on three types of fuels: MOX, nitride and metal is compared and discussed. In the fourth generation NPP paradigm, especially for Pb-Bi cooled fast reactors, inherent safety capability is necessary against some standard accidents such as unprotected loss of flow (ULOF), unprotected rod run-out transient over power (UTOP), unprotected loss of heat sink (ULOHS). Selection of fuel type will have important impact on the overall system safety performance. The results of safety analysis of long life Pb-Bi cooled fast reactors without on-site fuelling using nitride, MOX and metal fuel have been performed. The reactors show the inherent safety pattern with enough safety margins during ULOF and UTOP accidents. For MOX fuelled reactors, ULOF accident is more severe than UTOP accident while for nitride fuelled cores UTOP accident may push power much higher than that comparable MOX fuelled cores. (author)

  2. Intercomparison of the means of calibration relating to the measuring assemblies used in the refuelling of motor vehicles with liquefied petroleum gases

    Energy Technology Data Exchange (ETDEWEB)

    Silvert, L.; Verdonck, J.

    1982-09-01

    The calibration systems of all member countries equipped to calibrate road-side pumps delivering liquified petroleum gas (LPG) were included in the intercomparison - double water displacement gauge (F) - simple water displacement gauge (D) - ''bombola'' (I) - master meter (UK). The comparison was made with a pipe prover (piston) which circulated between the participating laboratories. The results have shown that only the simple water displacement gauge and the pipe prover have adequate properties for the metrological calibration.

  3. Reactivity considerations for the on-line refuelling of a pebble bed modular reactor—Illustrating safety for the most reactive core fuel load

    International Nuclear Information System (INIS)

    Reitsma, Frederik

    2012-01-01

    In the multi-pass fuel management scheme employed for the pebble bed modular reactor the fuel pebbles are re-circulated until they reach the target burn-up. The rate at which fresh fuel is loaded and burned fuel is discharged is a result of the core neutronics cycle analysis but in practice (on the plant) this has to be controlled and managed by the fuel handling and storage system and use of the burnup measurement system. The excess reactivity is the additional reactivity available in the core during operating conditions that is the result of loading a fuel mixture in the core that is more reactive (less burned) than what is required to keep the reactor critical at full power operational conditions. The excess reactivity is balanced by the insertion of the control rods to keep the reactor critical. The excess reactivity allows flexibility in operations, for example to overcome the xenon build up when power is decreased as part of load follow. In order to limit reactivity excursions and to ensure safe shutdown the excess reactivity and thus the insertion depth of the control rods at normal operating conditions has to be managed. One way to do this is by operational procedures. The reactivity effect of long-term operation with the control rods inserted deeper than the design point is investigated and a control rod insertion limit is proposed that will not limit normal operations. The effects of other phenomena that can increase the power defect, such as higher-than-expected fuel temperatures, are also introduced. All of these cases are then evaluated by ensuring cold shutdown is still achievable and where appropriate by reactivity insertion accident analysis. These aspects are investigated on the PBMR 400 MW design.

  4. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Supporting MELCOR calculations, Volume 6, Part 2

    International Nuclear Information System (INIS)

    Kmetyk, L.N.; Brown, T.D.

    1995-03-01

    To gain a better understanding of the risk significance of low power and shutdown modes of operation, the Office of Nuclear Regulatory Research at the NRC established programs to investigate the likelihood and severity of postulated accidents that could occur during low power and shutdown (LP ampersand S) modes of operation at commercial nuclear power plants. To investigate the likelihood of severe core damage accidents during off power conditions, probabilistic risk assessments (PRAs) were performed for two nuclear plants: Unit 1 of the Grand Gulf Nuclear Station, which is a BWR-6 Mark III boiling water reactor (BWR), and Unit 1 of the Surry Power Station, which is a three-loop, subatmospheric, pressurized water reactor (PWR). The analysis of the BWR was conducted at Sandia National Laboratories while the analysis of the PWR was performed at Brookhaven National Laboratory. This multi-volume report presents and discusses the results of the BWR analysis. The subject of this part presents the deterministic code calculations, performed with the MELCOR code, that were used to support the development and quantification of the PRA models. The background for the work documented in this report is summarized, including how deterministic codes are used in PRAS, why the MELCOR code is used, what the capabilities and features of MELCOR are, and how the code has been used by others in the past. Brief descriptions of the Grand Gulf plant and its configuration during LP ampersand S operation and of the MELCOR input model developed for the Grand Gulf plant in its LP ampersand S configuration are given

  5. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Supporting MELCOR calculations, Volume 6, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    Kmetyk, L.N.; Brown, T.D. [Sandia National Labs., Albuquerque, NM (United States)

    1995-03-01

    To gain a better understanding of the risk significance of low power and shutdown modes of operation, the Office of Nuclear Regulatory Research at the NRC established programs to investigate the likelihood and severity of postulated accidents that could occur during low power and shutdown (LP&S) modes of operation at commercial nuclear power plants. To investigate the likelihood of severe core damage accidents during off power conditions, probabilistic risk assessments (PRAs) were performed for two nuclear plants: Unit 1 of the Grand Gulf Nuclear Station, which is a BWR-6 Mark III boiling water reactor (BWR), and Unit 1 of the Surry Power Station, which is a three-loop, subatmospheric, pressurized water reactor (PWR). The analysis of the BWR was conducted at Sandia National Laboratories while the analysis of the PWR was performed at Brookhaven National Laboratory. This multi-volume report presents and discusses the results of the BWR analysis. The subject of this part presents the deterministic code calculations, performed with the MELCOR code, that were used to support the development and quantification of the PRA models. The background for the work documented in this report is summarized, including how deterministic codes are used in PRAS, why the MELCOR code is used, what the capabilities and features of MELCOR are, and how the code has been used by others in the past. Brief descriptions of the Grand Gulf plant and its configuration during LP&S operation and of the MELCOR input model developed for the Grand Gulf plant in its LP&S configuration are given.

  6. Brief review of 1995 events at Ukraine's NPPs. Report on the ChNPP unit 1 of November 27.1995 ''strict regime area premises contamination after reactor refuelling''

    International Nuclear Information System (INIS)

    Lomakin, V.

    1996-01-01

    In 1995 number of events at NPP had considerably decreased as compared with that for previous 1992-94, amounted in 87. In particular, as compared with 1994, events number had decreased by 36%. It characterizes a total improvement of current NPPs safety level during 1995. The most events number as recalculated per single unit was at the South Ukraine NPP - 8. The least - at the ChNPP - 4 in total, and 1,3 per unit. Decreasing of a total events number for 1995 did also accordingly reduce other quantitative system indices which reflect state of NPPs safety level. Among event root causes, as it was before, ''administrative management deficiencies'' and ''staff training deficiencies'' are still dominanting. ''Human factor'' issues are still pending for NPPs safety, despite of considerable efforts applied to improved efficiency of correcting measures aimed at their solution. Of sufficient importance for events system development in 1995 was the work implemented at the SSTC NRS/NRA as regards preparation of modern edition of the ''Regulation on order of NPP events investigation and account''. The IAEA/Nuclear Safety Division rendered a sufficient assistance for this work to be done through arrangement of advisory help to Ukrainian specialists from international experts. 2 figs, 8 diagrams

  7. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal fire events for Plant Operational State 5 during a refueling outage. Volume 3

    International Nuclear Information System (INIS)

    Lambright, J.; Yakle, J.

    1994-07-01

    This report, Volume 3, presents the details of the analysis of core damage frequency due to fire during shutdown Plant Operational State 5 at the Grand Gulf Nuclear Station. Insights from previous fire analyses (Peach Bottom, Surry, LaSalle) were used to the greatest extent possible in this analysis. The fire analysis was fully integrated utilizing the same event trees and fault trees that were used in the internal events analysis. In assessing shutdown risk due to fire at Grand Gulf, a detailed screening was performed which included the following elements: (a) Computer-aided vital area analysis; (b) Plant inspections; (c) Credit for automatic fire protection systems; (d) Recovery of random failures; (e) Detailed fire propagation modeling. This screening process revealed that all plant areas had a negligible (<1.0E-8 per year) contribution to fire-induced core damage frequency

  8. Improvements in or relating to nuclear reactors

    International Nuclear Information System (INIS)

    Savin, N.I.; Khramov, D.A.; Filippov, V.J.; Bugrov, V.V.

    1979-01-01

    A nuclear reactor is described, comprising a core accommodating a plurality of fuel assemblies and a refuelling device for replacing spent fuel assemblies. The design of the fuel assembly and of the refuelling device, and the method of carrying out the refuelling operation, are specified. (U.K.)

  9. Pellet injectors for JET

    International Nuclear Information System (INIS)

    Andelfinger, C.; Buechl, K.; Lang, R.S.; Schilling, H.B.; Ulrich, M.

    1981-09-01

    Pellet injection for the purpose of refuelling and diagnostic of fusion experiments is considered for the parameters of JET. The feasibility of injectors for single pellets and for quasistationary refuelling is discussed. Model calculations on pellet ablation with JET parameters show the required pellet velocity ( 3 ). For single pellet injection a light gas gun, for refuelling a centrifuge accelerator is proposed. For the latter the mechanical stress problems are discussed. Control and data acquisition systems are outlined. (orig.)

  10. Logistics and Maintenance Options to Support the P-8A Poseidon’s Expeditionary Mission

    Science.gov (United States)

    2010-06-01

    Equipment HOA Horn Of Africa ICD Initial Capabilities Document IFR In Flight Refueling ISR Intelligence Surveillance and Reconnaissance JOA...will transition to the new MPRF platform 18 one base and one squadron at a time beginning with the Fleet Readiness Squadron ( FRS ) and VP squadrons...and is equipped with in a universal aerial refueling receptacle that will provide In-Flight Refueling ( IFR ) capability. This new in-flight

  11. A Reliable, Efficient Cryogenic Propellant Mixing Pump With No Moving Parts, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Refueling spacecraft in space offers tremendous benefits for increased spacecraft payload capacity and reduced launch cost. However, there are several key challenges...

  12. A fast-running fuel management program for a CANDU reactor

    International Nuclear Information System (INIS)

    Choi, Hangbok

    2000-01-01

    A fast-running fuel management program for a CANDU reactor has been developed. The basic principle of this program is to select refueling channels such that the reference reactor conditions are maintained by applying several constraints and criteria when selecting refueling channels. The constraints used in this program are the channel and bundle power and the fuel burnup. The final selection of the refueling channel is determined based on the priority of candidate channels, which enhances the reactor power distribution close to the time-average model. The refueling simulation was performed for a natural uranium CANDU reactor and the results were satisfactory

  13. News | Argonne National Laboratory

    Science.gov (United States)

    to give second life to EV batteries Yemen News National Lab Licensing Hydrogen Refueling Method Could Computing Center Centers, Institutes, and Programs RISCRisk and Infrastructure Science Center Other

  14. DUPIC fuel performance from reactor physics viewpoint

    International Nuclear Information System (INIS)

    Choi, H.; Rhee, B.W.; Park, H.

    1995-01-01

    A preliminary study was performed for the evaluation of Stress Corrosion Cracking (SCC) parameters of nominal DUPIC fuel in CANDU reactor. For the reference 2-bundle shift refueling scheme, the predicted ramped power and power increase of the 43-element DUPIC fuel in the equilibrium core are below the SCC thresholds of CANDU natural uranium fuel. For 4-bundle shift refueling scheme, the envelope of element ramped power and power increase upon refueling are 8% and 44% higher than those of 2-bundle shift refueling scheme on the average, respectively, and both schemes are not expected to cause SCC failures. (author)

  15. Redmedial Action Plan for the Risk-Based Remediation of Site ST14 (SWMU 68), LPSTID 104819; the Former Base Refueling Area (A0C7); the French Underdrain System (SWMU 64); and the North Oil/Water Separator (SWMU 67), Carswell Air Force Base, Naval Air Station Fort Worth Joint Reserve Base, Texas. Volume 1: Report

    National Research Council Canada - National Science Library

    1997-01-01

    ...) to prepare a remedial action plan (RAP) in support of a risk-based remediation decision for soil and groundwater contaminated with fuel hydrocarbons at Site ST14 at Carswell Air Force Base (AFB), Texas...

  16. User manual of Visual Balan V. 1.0 Interactive code for water balances and refueling estimation; Manual del usuario del programa Visual Balan V. 1.0. Codigo interactivo para la realizacion de balances hidrologicos y la estimacion de la recarga

    Energy Technology Data Exchange (ETDEWEB)

    Samper, J.; Huguer, L.; Ares, J.; Garcia, M. A. [Universidad de La Coruna (Spain)

    1999-07-01

    This document contains the Users Manual of Visual Balan V1.0, an updated version of Visual Balan V0.0 (Samper et al., 1997). Visual Balan V1.0 performs daily water balances in the soil, the unsaturated zone and the aquifer in a user-friendly environment which facilitates both the input data process and the postprocessing of results. The main inputs of the balance are rainfall and irrigation while the outputs are surface runoff, evapotranspiration, interception, inter flow and groundwater flow. The code evaluates all these components in a sequential manner by starting with rainfall and irrigation, which must be provided by the user, and continuing with interception, surface runoff, evapotranspiration, and potential recharge (water flux crossing the bottom of the soil). This potential recharge is the input to the unsaturated zone where water can flow horizontally as subsurface flow (inter flow) or vertically as percolation into the aquifer. (Author)

  17. Final Rule for Control of Air Pollution From New Motor Vehicles and New Motor Vehicle Engines: Evaporative and Refueling Emission Regulations for Gasolineand Methanol-Fueled Light-Duty Vehicles and Light-Duty Trucks and Heavy-Duty Vehicles; Technical Amen

    Science.gov (United States)

    On March 24, 1993 EPA finalized a new test procedure to measure evaporative emissions from motor vehicles. The amendments modify several of the test procedure’s tolerances, equipment specifications, and procedural steps.

  18. Composition of fuel stores and digestive limitations to fuel deposition rate in the long-distance migratory thrush nightingale, Luscinia luscinia

    NARCIS (Netherlands)

    Klaassen, M.R.J.; Lindström, A.; Zijlstra, R.

    1997-01-01

    During their autumn migratory phase, thrush nightingales (Luscinia luscinia) previously starved for 2 d were allowed to refuel under three different ambient temperature conditions (-7 degrees, 7 degrees, and 22 degrees C). During the refueling period, as well as during the preceding control and

  19. Estimation of CANDU reactor zone controller level by generalized perturbation method

    International Nuclear Information System (INIS)

    Kim, Do Heon; Kim, Jong Kyung; Choi, Hang Bok; Roh, Gyu Hong; Yang, Won Sik

    1998-01-01

    The zone controller level change due to refueling operation has been studied using a generalized perturbation method. The generalized perturbation method provides sensitivity of zone power to individual refueling operation and incremental change of zone controller level. By constructing a system equation for each zone power, the zone controller level change was obtained. The details and a proposed model for future work are described

  20. Quantifying the European Strategic Airlift Gap

    Science.gov (United States)

    2013-06-01

    Refueling and other Exchanges of Services ( ATARES ) is a mechanism to enable exchanges in kind of AT, Air Refueling and other services between member...Interview) http://www.nato.int/docu/review/2007/issue1/ english /interview.html Hood, J. D. (April 2009). NATO strategic airlift: Capability or continued

  1. The 1 Percent Under Siege?

    DEFF Research Database (Denmark)

    Harrington, Brooke

    2016-01-01

    By exposing the sheer scale of offshore finance, the Panama Papers have re-fuelled global resentment towards tax-avoiding elites. Are the rich immoral?......By exposing the sheer scale of offshore finance, the Panama Papers have re-fuelled global resentment towards tax-avoiding elites. Are the rich immoral?...

  2. Objectives of Experimental Validation of Mechanical Equipment for BN-1200 Reactor Plant

    International Nuclear Information System (INIS)

    Timofeev, A.V.; Lyubimov, M.A.

    2013-01-01

    Conclusion: Fabricating and testing the pilot specimens of CRDMs, mockups of main elevator units, and cantilever refueling mechanism make it possible to validate their design. Positive testing results will make it possible to start the work on developing: • final designs of the elevator and cantilever refueling mechanism; • manufacturing design documentation on CRDM prototypes

  3. 77 FR 35279 - Approval and Promulgation of Implementation Plans; Arizona; Update to Stage II Gasoline Vapor...

    Science.gov (United States)

    2012-06-13

    ... because the exemptions as applied to the race cars themselves and to marine and aircraft refueling... evaporative emissions captured, as in the cases of late model rental cars refueling at rental car facilities and newly manufactured cars being fueled for the first time at automobile assembly plants. Table 1...

  4. 76 FR 82079 - AP1000 Design Certification Amendment

    Science.gov (United States)

    2011-12-30

    ... generators, the refueling water storage tank, and various equipment for power generation, refueling, and... in settling of any resultant debris) to facilitate heat transfer to the containment vessel and for...). The source of water for the evaporative cooling is the passive containment cooling water storage tank...

  5. Economic analysis of fuel management philosophy amendment in the second Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Cai Guangming

    2006-01-01

    In order to improve economic benefit, the Second Qinshan Nuclear Power Plant prepares to amend its fuel management philosophy after several fuel cycles. Economic evaluation is necessary before amendment of fuel management philosophy. Strong points and shortcomings are compared in this paper between yearly 1/4 refueling philosophy and 18 months refueling philosophy. (authors)

  6. 78 FR 35058 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-06-11

    ... submitted in a timely fashion based on the availability of the subsequent information. For further details...-cycle 23 refueling outage, currently scheduled for the fall of 2014, and shall be implemented for McGuire 2 within 30 days of the completion of the facility's end-of-cycle 22 refueling outage, currently...

  7. ND online software development for data acquisition of replacement operations of fuel assemblies of Atucha I Nuclear power plant

    International Nuclear Information System (INIS)

    Calvo, Maria Dolores; Wentzeis, Luis

    2012-01-01

    The ND Online software was developed in order to acquire data on a real-time basis of the refueling operations at the Atucha I nuclear power plant. The fuel elements containing slightly enriched uranium dioxide are located in the nuclear reactor core inside the cooling channels. The refueling operations are made periodically while the reactor is operating at full power. The acquired signals during the refueling operations are: pressure, force and position of the fuel element. In order to improve the safety and availability of the installation, monitoring of the refueling operations is important for the early detection of anomalies related to the fuel element itself, the cooling channels or the refueling machine (author)

  8. Optimization of the overall energy consumption in cascade fueling stations for hydrogen vehicles

    DEFF Research Database (Denmark)

    Rothuizen, Erasmus Damgaard; Rokni, Masoud

    2014-01-01

    of refueling stations as a function of number of tanks, volume of the tanks and the pressure in the tanks. This is done for a complete refueling cycle. It is found that the energy consumption decreases with the number of tanks approaching an exponential function. The compressor accounts for app. 50......% of the energy consumption. Going from one tank to three tanks gives an energy saving of app. 30%. Adding more than four tanks the energy saving per extra added tank is less than 4%. The optimal numbers of tanks in the cascade system are three or four....... the vehicles. The cascade system at the station has to be refueled as the tank sizes are limited by the high pressures. The process of filling a vehicle and afterward bringing the tanks in refueling station back to same pressures, are called a complete refueling cycle. This study analyzes power consumption...

  9. Oxidative Stress and Genotoxicity of Long-Term Occupational Exposure to Low Levels of BTEX in Gas Station Workers

    Directory of Open Access Journals (Sweden)

    Feng Xiong

    2016-12-01

    Full Text Available Atmospheric benzene, toluene, ethylbenzene, and xylenes (BTEX can lead to multiple health injuries. However, what remains uncertain is the effect of long-term exposure to low levels of BTEX. Thus, we determined the BTEX levels in the air from the refueling and office areas in gas stations. Then we collected workers’ (200 refueling vs. 52 office workers peripheral blood samples to analyze the serum total-superoxide dismutase (T-SOD, glutathione (GSH, malondialdehyde (MDA, and 8-hydroxydeoxyguanosine (8-OHdG levels. DNA damage was analyzed by the comet assay and micronucleus test in buccal epithelial cells. We found that the levels of BTEX in refueling areas were significantly higher than those in office areas (p < 0.001. The serum T-SOD and GSH of refueling workers were significantly lower than those in office workers (p < 0.001. By contrast, the serum MDA and 8-OHdG of refueling workers were significantly higher than those of office workers (p < 0.001, MDA; p = 0.025, 8-OHdG. Furthermore, tail and Olive tail moments in refueling workers were longer (p = 0.004, tail moment; p = 0.001, Olive tail moment, and the micronucleus rate was higher (p < 0.001 than those in office workers. Taken together, long-term exposure to low levels of BTEX may reduce the antioxidant ability and increase the risk of DNA damage in refueling workers of gas stations.

  10. An optimum fuel management method based on CANDU in-core detector readings

    International Nuclear Information System (INIS)

    Jeong, Chang Joon; Choi, Hang Bok

    2001-01-01

    In this study, a new optimal fuel management method is developed for a CANDU 600 MWe (CANDU-6) reactor. At first, an efficient power mapping method has been developed, which provides an accurate core status of an operating CANDU reactor. Secondly, an optimum refueling channel selection method has been developed by an optimization theory. For the power mapping method, the measured detector readings are used as boundary conditions of the diffusion theory calculation with the Kalman filtering (DIKAL) method. The performance of the DIKAL method was assessed for various core states and applied to the calculation of power and flux distribution in the CANDU 6 reactor. Sensitivity studies have shown that DIKAL method is insensitive to the detector random and systematic errors. An optimal refueling simulation method (OPTIMA), practically applicable to a CANDU 6 reactor, has also been developed. The objective of the optimization is to reproduce the reference core performance during refueling simulation, while satisfying the operation limits of channel and bundle powers. The optimization process consists of two stages: i) elimination of candidate refueling channels by several constraints and ii) selection of refueling channels by a direct search method that uses sensitivity coefficients of channel power generated for the reference core. The elimination process sorts out an appropriate number of fuel channels suitable for refueling, considering the channel power, bundle power and fuel burnup. The optimum refueling channels are then selected such that the difference of power distribution from the reference is minimized. In order to demonstrate the applicability of the overall fuel management methodology developed in this study, the DIKAL-OPTIMA method was applied to Wolsong-3 reactor refueling simulation, which is a typical CANDU-6 reactor. The results of refueling simulation have shown that the method can be efficiently used for the performance analysis of the operating

  11. An optimum fuel management method based on CANDU in-core detector readings

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Joon; Choi, Hang Bok

    2001-01-01

    In this study, a new optimal fuel management method is developed for a CANDU 600 MWe (CANDU-6) reactor. At first, an efficient power mapping method has been developed, which provides an accurate core status of an operating CANDU reactor. Secondly, an optimum refueling channel selection method has been developed by an optimization theory. For the power mapping method, the measured detector readings are used as boundary conditions of the diffusion theory calculation with the Kalman filtering (DIKAL) method. The performance of the DIKAL method was assessed for various core states and applied to the calculation of power and flux distribution in the CANDU 6 reactor. Sensitivity studies have shown that DIKAL method is insensitive to the detector random and systematic errors. An optimal refueling simulation method (OPTIMA), practically applicable to a CANDU 6 reactor, has also been developed. The objective of the optimization is to reproduce the reference core performance during refueling simulation, while satisfying the operation limits of channel and bundle powers. The optimization process consists of two stages: i) elimination of candidate refueling channels by several constraints and ii) selection of refueling channels by a direct search method that uses sensitivity coefficients of channel power generated for the reference core. The elimination process sorts out an appropriate number of fuel channels suitable for refueling, considering the channel power, bundle power and fuel burnup. The optimum refueling channels are then selected such that the difference of power distribution from the reference is minimized. In order to demonstrate the applicability of the overall fuel management methodology developed in this study, the DIKAL-OPTIMA method was applied to Wolsong-3 reactor refueling simulation, which is a typical CANDU-6 reactor. The results of refueling simulation have shown that the method can be efficiently used for the performance analysis of the operating

  12. Optimization of travel salesman problem using the ant colony system and Greedy search

    International Nuclear Information System (INIS)

    Esquivel E, J.; Ordonez A, A.; Ortiz S, J. J.

    2008-01-01

    In this paper we present some results obtained during the development of optimization systems that can be used to design refueling and patterns of control rods in a BWR. These systems use ant colonies and Greedy search. The first phase of this project is to be familiar with these optimization techniques applied to the problem of travel salesman problem (TSP). The utility of TSP study is that, like the refueling design and pattern design of control rods are problems of combinative optimization. Even, the similarity with the problem of the refueling design is remarkable. It is presented some results for the TSP with the 32 state capitals of Mexico country. (Author)

  13. Management of main generator condition during long term plant shut down at Higashidori Nuclear Power Station Unit 1

    International Nuclear Information System (INIS)

    Kato, Seiji

    2014-01-01

    Higashidori Nuclear Power Station Unit 1 shut down on February 6, 2011 to start 4th refuel outage. On March 11, 2011, we keep going refuel outage on this moment a large earthquake occurred and tsunami was generated following it which called 'Great East Japan Earthquake'. Refuel outage takes 3 ∼ 5 months normally but Higashidori NPS still keeping shut down over 3 years due to some issues. In this paper, we introduce about management of Main generator condition during long term plant shut down situation in addition to normal plant shut down situation to keep well. (author)

  14. Automatic fuel charging machine for nuclear power plants

    International Nuclear Information System (INIS)

    Neda, Toshikazu; Aoki, Shigeo.

    1978-01-01

    Purpose: To enable smooth, safety and rapid refueling by automatically conducting a series of fuel exchange steps through the combination of calculations for fuel control and refueling works. Constitution: Processing operations are conducted based on various data from the memory unit of a computer that processes and stores various data inputted from a nuclear power plant, calculation systems stored in the memory unit of another computer, peripheral units such as typewriters and process input units. A refueling platform is operated by way of a platform control device and a platform driving device, and fuel exchange is conducted by the operation of a channel mounting and demounting device. (Yoshino, Y.)

  15. 3D display considerations for rugged airborne environments

    Science.gov (United States)

    Barnidge, Tracy J.; Tchon, Joseph L.

    2015-05-01

    The KC-46 is the next generation, multi-role, aerial refueling tanker aircraft being developed by Boeing for the United States Air Force. Rockwell Collins has developed the Remote Vision System (RVS) that supports aerial refueling operations under a variety of conditions. The system utilizes large-area, high-resolution 3D displays linked with remote sensors to enhance the operator's visual acuity for precise aerial refueling control. This paper reviews the design considerations, trade-offs, and other factors related to the selection and ruggedization of the 3D display technology for this military application.

  16. Non-Scanning 3D Imager for Autonomous Rendezvous and Docking

    Data.gov (United States)

    National Aeronautics and Space Administration — On-Orbit Satellite Servicing brings the practical options of repair, refueling, and assembly to space-based exploration and commercial space ventures. It allows one...

  17. Estimation of Uncertainty in Risk Assessment of Hydrogen Applications

    DEFF Research Database (Denmark)

    Markert, Frank; Krymsky, V.; Kozine, Igor

    2011-01-01

    Hydrogen technologies such as hydrogen fuelled vehicles and refuelling stations are being tested in practice in a number of projects (e.g. HyFleet-Cute and Whistler project) giving valuable information on the reliability and maintenance requirements. In order to establish refuelling stations the ...... probability and the NUSAP concept to quantify uncertainties of new not fully qualified hydrogen technologies and implications to risk management.......Hydrogen technologies such as hydrogen fuelled vehicles and refuelling stations are being tested in practice in a number of projects (e.g. HyFleet-Cute and Whistler project) giving valuable information on the reliability and maintenance requirements. In order to establish refuelling stations...... the permitting authorities request qualitative and quantitative risk assessments (QRA) to show the safety and acceptability in terms of failure frequencies and respective consequences. For new technologies not all statistical data might be established or are available in good quality causing assumptions...

  18. Palisades Nuclear Plant. First annual report of operations, 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Information is presented concerning operations, maintenance, shutdowns, personnel exposures, failed fuel, refueling, and radioactive effluent releases. The radiological and nonradiological environmental monitoring programs are summarized. Changes, tests and experiments will be submitted by August 31, 1976

  19. Technology Transition -- Lessons Learned from Fido (registered trademark)/PackBot (registered trademark)

    National Research Council Canada - National Science Library

    Parmentola, John A; Szkrybalo, Irena D

    2007-01-01

    .... The company is building a dog-like robot with the capability to run fast, traverse rough terrain, jump over obstacles 40 inches tall or 2 meters wide, and operate for 2 hours without refueling...

  20. Development and Testing of a High-Speed Real-Time Kinematic Precise DGPS Positioning System Between Two Aircraft

    National Research Council Canada - National Science Library

    Spinelli, Christopher J

    2006-01-01

    ... aerial-refueling and close formation flying. Although many of the current ambiguity resolution techniques use the residuals from the least squares position estimation to determine the true ambiguity set, this thesis presents a novel approach...

  1. Technical specifications: Byron Station Unit No. 1 (Docket No. STN 50-454). Appendix A to License No. NPF-23

    International Nuclear Information System (INIS)

    1984-10-01

    Specifications are presented concerning safety limits; reactor control systems; instrumentation; coolant circuits; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; design features; and administrative controls

  2. Redefining E-3 Core Competencies for Dominant Battlespace Knowledge in Future Combat Operations

    National Research Council Canada - National Science Library

    Kirkendall, David A

    2005-01-01

    .... The study focuses on how E-3 training is driven by the maintenance of a set of battle management core competencies rooted in the basics of aircraft tactical fluid control force accountability and aerial refueling...

  3. A Study of Fatigue and Performance Considerations in Air Mobility Cargo Aircrews Flying Transatlantic Missions

    National Research Council Canada - National Science Library

    Levin, Julian

    1997-01-01

    The U.S. Air Force Air Mobility Command (AMC) is responsible for movement of supplies and personnel, air refueling operations and air evacuation operations throughout the world in support of the United States' national interest...

  4. Global Vigilance, Reach, and Power? Made Possible only with a Robust Tanker Capability

    National Research Council Canada - National Science Library

    Uyehata, Stephen

    2005-01-01

    ...). Therefore, the CCs should place aerial refueling capability and the recapitalization of the multiple tanker fleets at the top of their integrated priority lists and should also take sufficient...

  5. Safety considerations for compressed hydrogen storage systems

    International Nuclear Information System (INIS)

    Gleason, D.

    2006-01-01

    An overview of the safety considerations for various hydrogen storage options, including stationary, vehicle storage, and mobile refueling technologies. Indications of some of the challenges facing the industry as the demand for hydrogen fuel storage systems increases. (author)

  6. Reply to INFCE/DEP./WG.8/48

    International Nuclear Information System (INIS)

    1978-12-01

    In replying to questions on WG8/UK/DOC 1, the design basis of the ''continuous refuelling'' is explained, and further comment is made on the disposal of waste silicon carbide and carbonaceous material, resulting from reprocessing operations

  7. Preliminary analysis on in-core fuel management optimization of molten salt pebble-bed reactor

    International Nuclear Information System (INIS)

    Xia Bing; Jing Xingqing; Xu Xiaolin; Lv Yingzhong

    2013-01-01

    The Nuclear Hot Spring (NHS) is a molten salt pebble-bed reactor featured by full power natural circulation. The unique horizontal coolant flow of the NHS demands the fuel recycling schemes based on radial zoning refueling and the corresponding method of fuel management optimization. The local searching algorithm (LSA) and the simulated annealing algorithm (SAA), the stochastic optimization methods widely used in the refueling optimization problems in LWRs, were applied to the analysis of refueling optimization of the NHS. The analysis results indicate that, compared with the LSA, the SAA can survive the traps of local optimized solutions and reach the global optimized solution, and the quality of optimization of the SAA is independent of the choice of the initial solution. The optimization result gives excellent effects on the in-core power flattening and the suppression of fuel center temperature. For the one-dimensional zoning refueling schemes of the NHS, the SAA is an appropriate optimization method. (authors)

  8. Technical specifications, Catawba Nuclear Station, Unit 1 (Docket No. 50-413). Appendix A to License No. NPF-35

    International Nuclear Information System (INIS)

    1985-01-01

    Information is presented concerning safety limits for operation of reactor control systems, power distribution, instrumentation, reactor coolant system, emergency core cooling system, containment system, electrical power systems, refueling operations, radioactive effluents, environmental monitoring, reactor site, and administrative aspects

  9. Technical specifications: McGuire Nuclear Station, Unit Nos. 1 and 2. Docket Nos. 50-369 and 50-370

    International Nuclear Information System (INIS)

    Anderson, F.

    1983-03-01

    Information is presented concerning safety limits for operation; control systems; power distribution limits; instrumentation; primary coolant circuit; emergency core cooling systems; containment systems; steam turbines and secondary coolant circuits; electrical equipment; refueling operations; radioactive effluents; and reactor site

  10. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

    This single page document is the November 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the production reactor.

  11. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

    This single page document is the October 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  12. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

    This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  13. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

    This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  14. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

    This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  15. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

    This single page document is the December 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  16. Three Mile Island Nuclear Station, Unit 1. Semiannual operating report No. 4, July--December 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Information is presented concerning operations, shutdowns, maintenance, changes, tests, experiments, radioactive effluent releases, solid radioactive waste, primary coolant chemistry, personel radiation, and refueling. Histograms of thermal power vs. time are included

  17. Improvements in or relating to nuclear reactors

    International Nuclear Information System (INIS)

    Timofeev, A.V.; Batjukov, V.I.; Fadeev, A.I.; Shapkin, A.F.; Shikhiyan, T.G.; Ordynsky, G.V.; Drachev, V.P.; Pogodin, E.N.

    1980-01-01

    A refuelling installation for nuclear reactor complexes is described for recharging the reactor vessels of such complexes with new fuel assemblies and for removing spent fuel assemblies from the reactor vessel. (U.K.)

  18. F-15 Intelligent Flight Control System and Aeronautics Research at NASA Dryden

    Science.gov (United States)

    Brown, Nelson A.

    2009-01-01

    This viewgraph presentation reviews the F-15 Intelligent Flight Control System and Aeronautics including Autonomous Aerial Refueling Demonstrations, X-48B Blended Wing Body, F-15 Quiet Spike, and NF-15 Intelligent Flight Controls.

  19. Technical specifications: Callaway Plant, Unit No. 1 (Docket No. STN 50-483). Appendix A to License No. NPF-30. Revision 1

    International Nuclear Information System (INIS)

    1984-10-01

    Revised specifications are presented concerning limiting safety system settings for control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical systems, refueling operations, radioactive effluents, and radiation environmental monitoring

  20. Pellet injection requirements for TORE SUPRA

    International Nuclear Information System (INIS)

    Lafferranderie, J.

    1986-01-01

    The main parameters of TORE SUPRA are outlined and pellet injection requirements to meet plasma density goals are discussed. Topics considered include plasma buildup, plasma refueling and penetration depth

  1. Semi-Autonomous Telerobotic Manipulation for On-Orbit Spacecraft Servicing and Assembly over Time-Delayed Telemetry

    Data.gov (United States)

    National Aeronautics and Space Administration — Despite the prevalence of this telerobotic surgery of humans, we still do not have the capability to service (refuel and repair) or assemble spacecraft on-orbit with...

  2. Practice and prospect of advanced fuel management and fuel technology application in PWR in China

    International Nuclear Information System (INIS)

    Xiao Min; Zhang Hong; Ma Cang; Bai Chengfei; Zhou Zhou; Wang Lei; Xiao Xiaojun

    2015-01-01

    Since Daya Bay nuclear power plant implemented 18-month refueling strategy in 2001, China has completed a series of innovative fuel management and fuel technology projects, including the Ling Ao Advanced Fuel Management (AFM) project (high-burnup quarter core refueling) and the Ningde 18-month refueling project with gadolinium-bearing fuel in initial core. First, this paper gives brief introduction to China's advanced fuel management and fuel technology experience. Second, it introduces practices of the advanced fuel management in China in detail, which mainly focuses on the implementation and progress of the Ningde 18-month refueling project with gadolinium-bearing fuel in initial core. Finally, the paper introduces the practices of advanced fuel technology in China and gives the outlook of the future advanced fuel management and fuel technology in this field. (author)

  3. Comparison of advanced LWR reactor core design strategies by the net present value method

    International Nuclear Information System (INIS)

    Belac, J.

    2002-12-01

    The following major topics are included: (i) Economic assessment of refuelling variants (Alternatives of economic assessment of refuelling variants; Net present value (NPV); Input parameters accounted for by the economic assessment model; Expressing cash flow for the NPV approach; Specific [unit] costs); (ii) Fuel cycle variants being compared; and (iii) Effect of Czech legislation on the economic indices and NPP fuel cycle assessment. (P.A.)

  4. What Is the Future for SOF in the Arctic?

    Science.gov (United States)

    2014-12-01

    typically a routine when coasting out over water, but they had been flying over the ocean for five-and-a-half hours, jumping from Shell to Chevron, and...checkpoint Shell , where the helicopters refueled while the C-130 climbed up to refuel from a Dutch KDC-135 tanker also supporting the mission. From...shales, oil sands-based synthetic crudes and derivative products (heavy oil, Orimulsion), coal-based liquid supplies, biomass -based liquid supplies, gas

  5. Improving the Cost Efficiency and Readiness of MC-130 Aircrew Training: A Case Study

    Science.gov (United States)

    2015-01-01

    Air Force VBA Visual Basic for Applications 1 AFSOC/A3T, "MC-130 Aircrew Training," Air Force...aircrew members have access to a co- located flight simulator, the proportion of training that is accomplished at a temporary duty...coordinate to have access to the aerial refueling track which is basically the airspace used to conduct aerial refueling. Crewmembers must also be

  6. Virtual reality in design, planning, operation and training related to the decommissioning of the Chernobyl NPP

    International Nuclear Information System (INIS)

    Mark, N.-K.; Johnsen, T.; Meyer, G.; Owre, F.

    2007-01-01

    Virtual Reality in refueling operation and maintenance training at Leningrad NPP has been recognized by Chernobyl NPP. Institute for Energy Technology's is establishing now the Chernobyl Decommissioning Visualization Centre to be used for planning and training the dismantling procedures in addition to presenting it to the authorities and the public. It will be ready in 2007. The first scenario will be the dismantling of the refueling machines

  7. PWR upper/lower internals shield

    Energy Technology Data Exchange (ETDEWEB)

    Homyk, W.A. [Indian Point Station, Buchanan, NY (United States)

    1995-03-01

    During refueling of a nuclear power plant, the reactor upper internals must be removed from the reactor vessel to permit transfer of the fuel. The upper internals are stored in the flooded reactor cavity. Refueling personnel working in containment at a number of nuclear stations typically receive radiation exposure from a portion of the highly contaminated upper intervals package which extends above the normal water level of the refueling pool. This same issue exists with reactor lower internals withdrawn for inservice inspection activities. One solution to this problem is to provide adequate shielding of the unimmersed portion. The use of lead sheets or blankets for shielding of the protruding components would be time consuming and require more effort for installation since the shielding mass would need to be transported to a support structure over the refueling pool. A preferable approach is to use the existing shielding mass of the refueling pool water. A method of shielding was devised which would use a vacuum pump to draw refueling pool water into an inverted canister suspended over the upper internals to provide shielding from the normally exposed components. During the Spring 1993 refueling of Indian Point 2 (IP2), a prototype shield device was demonstrated. This shield consists of a cylindrical tank open at the bottom that is suspended over the refueling pool with I-beams. The lower lip of the tank is two feet below normal pool level. After installation, the air width of the natural shielding provided by the existing pool water. This paper describes the design, development, testing and demonstration of the prototype device.

  8. In core-fuel management in approach to equilibrium of WWER-440 reactor; Prelazni rezim iskoriscenja goriva u nuklearnom reaktoru tipa VVER-440

    Energy Technology Data Exchange (ETDEWEB)

    Marinkovic, N [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1978-07-01

    For the need of in core fuel management and prediction of fuel cycle costs as well as operating of a nuclear power plant behaviour of main physical parameters and refueling scheme during approach to equilibrium operation are indispensable. An estimation of a refueling scheme during forst six years of exploitation for a commercially proven PWR reactor of WWER-440 type is shown in this paper. (author)

  9. A conceptual high flux reactor design with scope for use in ADS ...

    Indian Academy of Sciences (India)

    By design the flux level in the seed fuel has been kept lower than in the high flux trap zones so that the burning rate of the seed is reduced. Another important objective of the design is to maximize the time interval of refueling. As against a typical refueling interval of a few weeks in such high flux reactor cores, it is desired to ...

  10. Irresistable: Service Masks, Goldwater-Nichols, and Overcoming Service Barriers to JFACC

    Science.gov (United States)

    2016-06-10

    Air Forces IFR In Flight Refueling JCS Joint Chiefs of Staff JFACC Joint Force Air Component Commander JFC Joint Force Commander LOC Lines of...culture, diplomacy, and beyond.7 The focus is on the personalities that build and develop the technology and thus their impact on history. This broad...embarked Air Group 5 contained propeller and first-generation jets. In the days before in- flight-refueling ( IFR ), these aircraft could only manage a

  11. A study on the direct use of spent PWR fuel in CANDU reactors -Fuel management and safety analysis-

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Soo; Lee, Boh Wook; Choi, Hang Bok; Lee, Yung Wook; Cho, Jae Sun; Huh, Chang Wook [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The reference DUPIC fuel composition was determined based on the reactor safety, thermal-hydraulics, economics, and refabrication aspects. The center pin of the reference DUPIC fuel bundle is poisoned with natural dysprosium. The worst LOCA analysis has shown that the transient power and heat deposition of the reference DUPIC core are the same as those of natural uranium CANDU core. The intra-code comparison has shown that the accuracy of DUPIC physics code system is comparable to the current CANDU core design code system. The sensitivity studies were performed for the refuelling schemes of DUPIC core and the 2-bundle shift refuelling scheme was selected as the standard refuelling scheme of the DUPIC core. The application of 4-bundle shift refuelling scheme will be studied in parallel as the auto-refuelling method is improved and the reference core parameters of the heterogeneous DUPIC core are defined. The heterogeneity effect was analyzed in a preliminary fashion using 33 fuel types and the random loading strategy. The refuelling simulation has shown that the DUPIC core satisfies the current CANDU 6 operating limits of channel and bundle power regardless of the fuel composition heterogeneity. The 33 fuel types used in the heterogeneity analysis was determined based on the initial enrichment and discharge burnup of the PWR fuel. 90 figs, 62 tabs, 63 refs. (Author).

  12. H2T liquid hydrogen delivery system

    International Nuclear Information System (INIS)

    Roy, S.

    2002-01-01

    This Power Point presentation provides a preliminary evaluation of the cost of delivering liquid hydrogen produced in Quebec to hydrogen fuelled cars in Germany. The presentation describes the chain of events regarding liquid hydrogen delivery, beginning with the production of hydrogen from an initial source of hydro power. Water passes through an electrolyzer where hydrogen is liquefied and then placed into a container which is transported to market via truck, rail or tanker. Once transported, the hydrogen fuel is made available for consumers at refueling stations. The paper lists the costs related to transportation with reference to safety rules, pure transportation costs, leasing fees for the containers, and permission of customs duties for the import of hydrogen and export of empty containers between Quebec and Germany. A graph depicting a typical refueling station in Germany and the refueling events per hour was presented. For safety reasons, refueling is performed by a refueling robot. A blueprint of safety and protection distances at a refueling station was also presented. tabs., figs

  13. Rearrangement of fuel assemblies in the RBMK type reactors to flatten power distribution and improve the fuel cycle

    International Nuclear Information System (INIS)

    Mityaev, Yu.I.; Vikulov, V.K.

    1982-01-01

    A possibility of increasing the burnup of uranium fuel unloaded from the RBMK type reactors is investigated. Three variants of a two-zone reactor-refueling are considered: 1. the simplest variant of continuous refueling used at present, when the central and peripherical reactor zones are additionally fueled independently by similar fuel assemblies (FA); 2. the variant under which new FA are loaded to the peripherical zone and are used there up to the same burnup as in the first case, then all the peripherical FA (PFA) are rearranged to the centre and they are used there up to maximum burnup; 3. the same as in the second variant, but not all the PFA are rearranged to the centre but only FA with small fuel burnup. It is shown by calculation that average fuel burnup for the third refueling variant is several per cent higher at the optimal burnup of rearranged FA. Besides, flattening of fuel channel power is improved in this case, that permits to increase uranium enrichment and burnup at the same maximum power. It essentially improves economic parameters of the reactor. It is concluded that realization of the considered variant of fuel refueling will produce the most essential effect for reactors refueled without shutdown

  14. Risk-informed business modeling for nuclear power generation

    International Nuclear Information System (INIS)

    Liming, J.K.; Grantom, C.R.

    2000-01-01

    This paper documented the results of operations and maintenance cost-benefit-risk analysis (OMCBRA) of the currently planned refueling outage schedule profile and two potential alternate outage schedule strategy options for the South Texas Project Electric Generating Station (STPEGS). The objects, basic methodology, including bases and assumptions, results, conclusions, and recommendations developed for STPNOC during the project were presented. The application of the cost-benefit-risk analysis tools and techniques developed for the STPEGS staffs during the project were presented. The key question under consideration by the STPNOC leadership was whether or not there is an economic lower limit to planned refueling outage duration at STPEGS. The results showed that 14-day outage duration strategy was preferable in all assumption sets evaluated in this project. Therefore, this analysis shows that the 'point of diminishing returns' for outage duration reduction has not been reached between 14- and 30-day outage duration options. The sensitivity study on profitability versus refueling outage duration showed that the hypothetical optimum refueling outage duration was probably somewhere between 5 and 10 days. That is, given the bases and assumptions applied in this analysis, any reasonable options for reducing refueling outage duration below the current 21-day strategy would appear to be justified on cost-benefit-risk considerations. OMCBRA can be used to both monitor station overall economic performance as well as support change management and it can be applied to continually optimize station decision-making for maximum profitability. (M.N.)

  15. Safety assessment of ammonia as a transport fuel

    Energy Technology Data Exchange (ETDEWEB)

    Duijm, N.J.; Markert, F.; Lundtang paulsen, Jette

    2005-02-01

    This report describes the safety study performed as part of the EU supported project 'Ammonia Cracking for Clean Electric Power Technology' The study addresses the following activities: safety of operation of the ammonia-powered vehicle under normal and accident (collision) conditions, safety of transport of ammonia to the refuelling stations and safety of the activities at the refuelling station (unloading and refuelling). Comparisons are made between the safety of using ammonia and the safety of other existing or alternative fuels. The conclusion is that the hazards in relation to ammonia need to be controlled by a combination of technical and regulatory measures. The most important requirements are: - Advanced safety systems in the vehicle - Additional technical measures and regulations are required to avoid releases in maintenance workshops and unauthorised maintenance on the fuel system - Road transport of ammonia to refuelling stations in refrigerated form - Sufficient safety zones between refuelling stations and residential or otherwise public areas. When these measures are applied, the use of ammonia as a transport fuel wouldnt cause more risks than currently used fuels (using current practice). (au)

  16. Performance improvement of magnetized coaxial plasma gun by magnetic circuit on a bias coil

    Science.gov (United States)

    Edo, Takahiro; Matsumoto, Tadafumi; Asai, Tomohiko; Kamino, Yasuhiro; Inomoto, Michiaki; Gota, Hiroshi

    2016-10-01

    A magnetized coaxial plasmoid accelerator has been utilized for compact torus (CT) injection to refuel into fusion reactor core plasma. Recently, CT injection experiments have been conducted on the C-2/C-2U facility at Tri Alpha Energy. In the series of experiments successful refueling, i.e. increased particle inventory of field-reversed configuration (FRC) plasma, has been observed. In order to improve the performance of CT injector and to refuel in the upgraded FRC device, called C-2W, with higher confinement magnetic field, magnetic circuit consisting of magnetic material onto a bias magnetic coil is currently being tested at Nihon University. Numerical work suggests that the optimized bias magnetic field distribution realizes the increased injection velocity because of higher conversion efficiency of Lorenz self force to kinetic energy. Details of the magnetic circuit design as well as results of the test experiment and field calculations will be presented and discussed.

  17. Risk analysis of complex hydrogen infrastructures

    DEFF Research Database (Denmark)

    Markert, Frank; Marangon, Alessia; Carcassi, Marco

    2015-01-01

    Developing a future sustainable refuelling station network is the next important step to establish hydrogen as a fuel for vehicles and related services. Such stations will most likely be integrated in existing refuelling stations and result in multi-fuel storages with a variety of fuels being...... to improve the quality of biomass based fuels. Therefore, hydrogen supply and distribution chains will likely not only serve to fulfil the demands of refuelling, but may also be important for the wider electrical power and fuel industries. Based on an integrated hydrogen supply and distribution network...... assessment methodologies, and how functional models could support coherent risk and sustainability (Risk Assessment, Life Cycle Assessment /Life Cycle Costing) assessments, in order to find optimal solutions for the development of the infrastructure on a regional or national level....

  18. Preliminary Study for Inventories of Minor Actinides in Thorium Molten Salt Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Choong Wie; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2015-05-15

    It has different characteristic with the conventional reactors which use a solid fuel. It can continually supply the fuel by online refueling and reprocessing of minor actinides so that those can be separated and eliminated from the reactor. The MSR maintains steady state except initial stage and the reactor becomes stable. In this research, considering online refueling, bubbling and reprocessing, the basic concept for evaluation of the inventory of minor actinide in the molten salt reactor is driven using the Bateman equation. The simulation results, where REM and MCNP code from CNRS (Centre National de la Recherche Scientifique) applied to the concept equation are analyzed. The analysis of the basic concept was carried out for evaluation of the inventory of the minor actinides in MSR. It was thought that the inventories of the minor actinides should be evaluated by solving the modified Bateman equation due to the MSR characteristic of online refueling, chemical reprocessing and bubbling.

  19. The upgrade of integrity analysis module and the mechanical behavior evaluation for the assembly duct

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byoung Oon; Lee, Dong Uk; Kim, Young Il [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-05-01

    The high neutron fluxes and operating temperatures associated with KALIMER are inducing the important radiation damage phenomena, which can cause significant dimensional changes in the core components of the reactor.The thermo-mechanical analysis of the assembly ducts for KALIMER are mainly performed to evaluate the following items.1) change of reactivity. 2) force at pads on core assemblies. 3) withdrawal force at refueling. 4) loading and refueling deviation of assembly ducts. 5) bowing modes for control assembly. In this report, the model for the evaluation of reactivity change as well as the refueling model and the withdrawl force model are upgraded. And the reactivity change is considered as the most important parameter among the above items. Therefore, the sensitivity analyses mainly associated with reactivity change are carried out. As the results, the pad gap between the assembly ducts preliminary driven for keeping the (-) reactivity change. 9 refs., 24 figs., 2 tabs. (Author)

  20. Slovak Chernobyl /1976/

    International Nuclear Information System (INIS)

    Sveda, R.

    2007-01-01

    In this video-film history of Bohunice A-1 NPP is presented. The A-1 reactor was an experimental reactor, which during 1973 - 1977 this NPP produced electricity. In January 5, 1976 during refuelling of fuel elements one of them was hurled and carbon dioxide leaks into reactor hall. The operator Viliam Paces packed the hole with refuelling machine. In this film process of refuelling and this reactor accident are reconstructed and reasons are analysed. Two workers were killed outside the premises of the reactor hall. Direct participants as well as one son of the victim recall about this accident. After repairing of the reactor this nuclear power plant was again put into operation. But in February 22, 1977 the second accident (level 4 of the INES scale) occurred after which the nuclear power plant has been closed.

  1. Fuel management optimization for a PWR

    International Nuclear Information System (INIS)

    Dumas, M.; Robeau, D.

    1981-04-01

    This study is aimed to optimize the refueling pattern of a PWR. Two methods are developed, they are based on a linearized form of the optimization problem. The first method determines a feasible solution in two steps; in the first one the original problem is replaced by a relaxed one which is solved by the Method of Approximation Programming. The second step is based on the Branch and Bound method to find the feasible solution closest to the solution obtained in the first step. The second method starts from a given refueling pattern and tries to improve this pattern by the calculation of the effects of 2 by 2, 3 by 3 and 4 by 4 permutations on the objective function. Numerical results are given for a typical PWR refueling using the two methods

  2. Review of gas gun technology with emphasis on fusion fueling applications

    International Nuclear Information System (INIS)

    Flagg, R.F.

    1978-01-01

    A review is made of current light gas gun and related hyper-velocity launcher technology with emphasis on physical and technological limits, advantages, and disadvantages as they apply to injection requirements for refueling Tokamak type nuclear fusion reactors. It is shown that the mass and velocity requirements for refueling are well within the capabilities of the state of the art and can be produced by several of the different types of gun/launching devices. The practical problems of adapting this performance capability to the refueling task are addressed and some possible configurations are given including both single pellet and multiple pellet injection. A short bibliography is given for those who wish additional detailed information

  3. ALARA database value in future outage work planning and dose management

    International Nuclear Information System (INIS)

    Miller, D.W.; Green, W.H.

    1995-01-01

    ALARA database encompassing job-specific duration and man-rem plant specific information over three refueling outages represents an invaluable tool for the outage work planner and ALARA engineer. This paper describes dose-management trends emerging based on analysis of three refueling outages at Clinton Power Station. Conclusions reached based on hard data available from a relational database dose-tracking system is a valuable tool for planning of future outage work. The system's ability to identify key problem areas during a refueling outage is improving as more outage comparative data becomes available. Trends over a three outage period are identified in this paper in the categories of number and type of radiation work permits implemented, duration of jobs, projected vs. actual dose rates in work areas, and accuracy of outage person-rem projection. The value of the database in projecting 1 and 5 year station person-rem estimates is discussed

  4. Method for temporary shielding of reactor vessel internals

    International Nuclear Information System (INIS)

    Grimm, N.P.; Sejvar, J.

    1991-01-01

    This patent describes a method for shielding stored internals for reactor vessel annealing. It comprises removing nuclear fuel from the reactor vessel containment building; removing and storing upper and lower core internals under water in a refueling canal storage area; assembling a support structure in the refueling canal between the reactor vessel and the stored internals; introducing vertical shielding tanks individually through a hatch in the containment building and positioning each into the support structure; introducing horizontal shielding tanks individually through a hatch in the containment building and positioning each above the stored internals and vertical tanks; draining water from the refueling canal to the level of a flange of the reactor vessel; placing an annealing apparatus in the reactor vessel; pumping the remaining water from the reactor vessel; and annealing the reactor vessel

  5. Development of natural gas vehicles in China

    Energy Technology Data Exchange (ETDEWEB)

    Zongmin, Cheng

    1996-12-31

    Past decade and current status of development of natural gas vehicles (NGVs) in China is described. By the end of 1995, 35 CNG refueling stations and 9 LPG refueling stations had been constructed in 12 regions, and 33,100 vehicles had been converted to run on CNG or LPG. China`s automobile industry, a mainstay of the national economy, is slated for accelerated development over next few years. NGVs will help to solve the problems of environment protection, GHGs mitigation, and shortage of oil supply. The Chinese government has started to promote the development of NGVs. Projects, investment demand, GHG mitigation potential, and development barriers are discussed. China needs to import advanced foreign technologies of CNGs. China`s companies expect to cooperate with foreign partners for import of CNG vehicle refueling compressors, conversions, and light cylinders, etc.

  6. FLODIS: a computer model to determine the flow distribution and thermal response of the Fort St. Vrain reactor

    Energy Technology Data Exchange (ETDEWEB)

    Paul, D.D.

    1976-06-01

    FLODIS is a combined heat transfer and fluid flow analysis calculation written specifically for the core of the Fort St. Vrain reactor. It is a lumped-node representation of the 37 refueling regions in the active core. Heat conduction to the coolant and in the axial direction is represented; however, the effect of conduction between refueling regions is not included. The calculation uses the specified operating conditions for the reactor at power to determine appropriate loss coefficients for the variable orifices in each refueling region. Flow distributions following reactor trip and a reduction in coolant pressure and flow are determined assuming that the orifice coefficients remain constant. Iterative techniques are used to determine the distribution of coolant flow as a function of time during the transient. Results are presented for the evaluation of the transient for the Fort St. Vrain reactor following depressurization and cooling with two circulators operating at 8000 rpm.

  7. FLODIS: a computer model to determine the flow distribution and thermal response of the Fort St. Vrain reactor

    International Nuclear Information System (INIS)

    Paul, D.D.

    1976-06-01

    FLODIS is a combined heat transfer and fluid flow analysis calculation written specifically for the core of the Fort St. Vrain reactor. It is a lumped-node representation of the 37 refueling regions in the active core. Heat conduction to the coolant and in the axial direction is represented; however, the effect of conduction between refueling regions is not included. The calculation uses the specified operating conditions for the reactor at power to determine appropriate loss coefficients for the variable orifices in each refueling region. Flow distributions following reactor trip and a reduction in coolant pressure and flow are determined assuming that the orifice coefficients remain constant. Iterative techniques are used to determine the distribution of coolant flow as a function of time during the transient. Results are presented for the evaluation of the transient for the Fort St. Vrain reactor following depressurization and cooling with two circulators operating at 8000 rpm

  8. MCNP Simulations of End Flux Peaking in ACR-1000, 2.4 wt % {sup 235}U Fuel Bundles

    Energy Technology Data Exchange (ETDEWEB)

    Hill, Ian; Donnelly, Jim [Atomic Energy of Canada Limited (AECL), 2251 Speakman Drive, Mississauga, ON, L5K 1B2 (Canada)

    2008-07-01

    This paper examines the end flux peaking in ACR-1000 fuel bundles. Reactor physics simulations are performed with MCNP to assess the steady state end-flux peaking in an infinite lattice of ACR fuel, as well as to quantify the peaking that occurs during refuelling. 3-dimensional MCNP models are created based on the detailed geometry of the fuel bundle. Detailed position-dependent fuel compositions are obtained from MONTEBURNS which couples MCNP and ORIGIN2.2. Axial and radial power profiles are obtained for both fresh and mid-burnup fuel bundles in an infinite lattice. Subsequently an assessment of the impact of a refuelling transient on the power profiles is performed. The refuelling transient is found to increase the end flux peaking in the region adjacent to light water. (authors)

  9. Development of High Flux Isotope Reactor (HFIR) subcriticality monitoring methods

    International Nuclear Information System (INIS)

    Rothrock, R.B.

    1991-01-01

    Use of subcritical source multiplication measurements during refueling has been investigated as a possible replacement for out-of-reactor subcriticality measurements formerly made on fresh HFIR fuel elements at the ORNL Critical Experiment Facility. These measurements have been used in the past for preparation of estimated critical rod positions, and as a partial verification, prior to reactor startup, that the requirements for operational shutdown margin would be met. Results of subcritical count rate data collection during recent HFIR refuelings and supporting calculations are described illustrating the intended measurement method and its expected uncertainty. These results are compared to historical uses of the out-of-reactor core measurements and their accuracy requirements, and a planned in-reactor test is described which will establish the sensitivity of the method and calibrate it for future routine use during HFIR refueling. 2 refs., 1 fig., 2 tabs

  10. ALARA database value in future outage work planning and dose management

    Energy Technology Data Exchange (ETDEWEB)

    Miller, D.W.; Green, W.H. [Clinton Power Station Illinois Power Co., IL (United States)

    1995-03-01

    ALARA database encompassing job-specific duration and man-rem plant specific information over three refueling outages represents an invaluable tool for the outage work planner and ALARA engineer. This paper describes dose-management trends emerging based on analysis of three refueling outages at Clinton Power Station. Conclusions reached based on hard data available from a relational database dose-tracking system is a valuable tool for planning of future outage work. The system`s ability to identify key problem areas during a refueling outage is improving as more outage comparative data becomes available. Trends over a three outage period are identified in this paper in the categories of number and type of radiation work permits implemented, duration of jobs, projected vs. actual dose rates in work areas, and accuracy of outage person-rem projection. The value of the database in projecting 1 and 5 year station person-rem estimates is discussed.

  11. Preliminary Study for Inventories of Minor Actinides in Thorium Molten Salt Reactor

    International Nuclear Information System (INIS)

    Lee, Choong Wie; Kim, Hee Reyoung

    2015-01-01

    It has different characteristic with the conventional reactors which use a solid fuel. It can continually supply the fuel by online refueling and reprocessing of minor actinides so that those can be separated and eliminated from the reactor. The MSR maintains steady state except initial stage and the reactor becomes stable. In this research, considering online refueling, bubbling and reprocessing, the basic concept for evaluation of the inventory of minor actinide in the molten salt reactor is driven using the Bateman equation. The simulation results, where REM and MCNP code from CNRS (Centre National de la Recherche Scientifique) applied to the concept equation are analyzed. The analysis of the basic concept was carried out for evaluation of the inventory of the minor actinides in MSR. It was thought that the inventories of the minor actinides should be evaluated by solving the modified Bateman equation due to the MSR characteristic of online refueling, chemical reprocessing and bubbling

  12. Female Reproductive Effects of Exposure to Jet Fuel at U.S. Air Force Bases

    Science.gov (United States)

    1998-11-01

    first breath sample until the Monday morning ofyour final breath sample. Avoid self-service refueling of your vehicle or lawn mower this week (outside of...fuel the lawn mower and mow the lawn for her - Post-pone painting, spraying pesticides/insecticides or using solvents if she might be in the area and...U No U_ 2. In the PAST WEEK, that is, one week ago today, did you... a).. .use the self-service tank when refueling of your vehicle or lawn mower this

  13. AUTOSORO: A fuel management study program for Ontario Hydro CANDU reactors

    International Nuclear Information System (INIS)

    Wilk, L.

    1988-01-01

    A computer program, AUTOSORO, has been developed to automatically simulate an Ontario Hydro CANDU reactor core for any time duration according to user-defined on-power refuelling criteria. It is a three-dimensional two-group diffusion code coupled to refuelling decision logic at three screening levels: burnup, coupled neighbor, full-core. A central feature is a projected local-iteration scheme for predicting fuelling-induced local neutron flux changes. Comparisons of AUTOSORO results with actual histories demonstrate that it will be an excellent productivity tool for future in-core fuel management studies, reducing several man-months of effort to several man-hours

  14. Ontario Hydro Pickering Generating Station fuel handling system performance

    International Nuclear Information System (INIS)

    Underhill, H.J.

    1986-01-01

    The report briefly describes the Pickering Nuclear Generating Station (PNGS) on-power fuel handling system and refuelling cycle. Lifetime performance parameters of the fuelling system are presented, including station incapability charged to the fuel handling system, cost of operating and maintenance, dose expenditure, events causing system unavailability, maintenance and refuelling strategy. It is concluded that the 'CANDU' on-power fuelling system, by consistently contributing less than 1% to the PNGS incapability, has been credited with a 6 to 20% increase in reactor capacity factor, compared to off-power fuelling schemes. (author)

  15. Design of hoisting device used in nuclear power plants. KTA safety engineering code. Draft amendment, as of 6/98

    International Nuclear Information System (INIS)

    1998-06-01

    The draft amendment specifies, according to the hazards involved, (a) the general provisions, (b) additional provisions supplementing the general provisions, (c) more stringent provisions relating to aggravated risks, applicable to lifting gear, and (d) additional requirements for elevators in reactor containments and refuelling equipment, to be taken into account in the design of hoisting device used in nuclear power plants. The term hoisting device in this context covers elevators, cranes, winches, trolleys, load carrying equipment, and LWR refuelling machines as are used in nuclear power plants. (orig./CB) [de

  16. Integrated service of charge activities; Servicio integrado de actividades de recarga

    Energy Technology Data Exchange (ETDEWEB)

    Rojo Perez, P. L.; Llibre Fugueras, E.; Alvarez Gonzalez, P.

    2014-07-01

    The set of works that includes a stop for refueling of a nuclear power plant requires a huge effort of coordination between the central and the different contractors finally running the works. These efforts must be consistent with the objectives of the recharge in terms of safety, quality and completion of the program, all of them are listed in the Guide EPRI Effective Refueling Outage Preparation and Execution Guidance. In this context, Tecnatom, Westinghouse and Enusa created the UTE-TWE with the aim of improving the service provided to ANAV for units of Asco I and II and Vandellos II. (Author)

  17. Application of the low disturbances theory in operation calculations of the BMK reactor

    International Nuclear Information System (INIS)

    Isaev, N.V.; Shmonin, Yu.V.; Pogosbekyan, L.R.; Druzhinin, V.E.

    1985-01-01

    Calculation algorithm of direct and contingent tasks in a two-group diffusion approximation for RBMK-1000 of Smolensk-1 nuclear power plant is presented. Examples of numeric calculation of the reactivity change caused by neutron field disturbance reactivity effect in case of refueling, refueling, rate and reactivity reserve on control rods are given. Calculations are made according to PEPO-program. The program is written in FORTRAN-4 for ES computer. The modificated low disturbances theory used in this program allows to reduce sufficiently the calculation error

  18. Ultrasonic inspection of liquid-metal-filled austenitic stainless steel piping welds

    International Nuclear Information System (INIS)

    Mech, S.J.; Martin, J.D.

    1982-01-01

    The goal of this effort is to reliably detect a crack extending 25 to 50% through the wall of Schedule 40 sodium filled pipe at refueling temperatures (204 0 C [400 0 F]) using remote examination techniques. The task of demonstrating a prototype ultrasonic ISI system under simulated refueling conditions was laid out in two phases. The first phase was initiation of long-lead efforts which were key elements of a practical prototype system, including ultrasonic signal analysis efforts and laboratory prototype support systems. The second phase, dependent on successful completion of the first, consisted of development and demonstration of a prototype system in a simulated ISI environment

  19. TELESCOPE sipping - a proven fuel leak detection system

    International Nuclear Information System (INIS)

    Deleryd, R.; Collin, P.

    1996-01-01

    The advantages of the TELESCOPE sipping method are: For BWRs: clamp-on sipping nozzle, which attaches easily to the grapple of the telescope mast on the refuelling platform, but does not affect its operation; no heavy and large sipping bells have to be operated in the core with risk of damage, entangled hoses or lifting rods/wires; the sipping can also be performed for testing long time storaged fuel in the spent fuel pool. For PWRs: simple attachment of water suction hose or tube to the refuelling platform mast. (orig./DG)

  20. Development of a graphical interface computer code for reactor fuel reloading optimization

    International Nuclear Information System (INIS)

    Do Quang Binh; Nguyen Phuoc Lan; Bui Xuan Huy

    2007-01-01

    This report represents the results of the project performed in 2007. The aim of this project is to develop a graphical interface computer code that allows refueling engineers to design fuel reloading patterns for research reactor using simulated graphical model of reactor core. Besides, this code can perform refueling optimization calculations based on genetic algorithms as well as simulated annealing. The computer code was verified based on a sample problem, which relies on operational and experimental data of Dalat research reactor. This code can play a significant role in in-core fuel management practice at nuclear research reactor centers and in training. (author)

  1. Determination of the sources of the airborne physico-chemical 131I species in a PWR power plant

    International Nuclear Information System (INIS)

    Deuber, H.; Wilhelm, J.G.

    1978-01-01

    In a 1300 MWE PWR power plant the sources of the airborne 131 I species were determined over a period of 5 months. During power operation the main source of the radiologically decisive elemental 131 I was the exhaust from the hoods in which samples from the primary coolant are taken and processed. During refueling outage elemental 131 I was mainly contributed by the containment purge air. By efficient filtration of these exhausts, a reduction of the ingestion dose, caused by the total 131 I stack release, by a factor of nearly 4 during power operation and of possibly 10 during refueling outage can be accomplished. (author)

  2. A generalized perturbation program for CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Yang, Won Sik [Chosun University, Kwangju (Korea, Republic of)

    1999-12-31

    A generalized perturbation program has been developed for the purpose of estimating zonal power variation of a CANDU reactor upon refueling operation. The forward and adjoint calculation modules of RFSP code were used to construct the generalized perturbation program. The numerical algorithm for the generalized adjoint flux calculation was verified by comparing the zone power estimates upon refueling with those of forward calculation. It was, however, noticed that the truncation error from the iteration process of the generalized adjoint flux is not negligible. 2 refs., 1 figs., 1 tab. (Author)

  3. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  4. SISTEM PENDUKUNG KEPUTUSAN MENGGUNAKAN METODE PROMETHEE (STUDI KASUS : STASIUN PENGISIAN BAHAN BAKAR UMUM

    Directory of Open Access Journals (Sweden)

    Hendy Ayusta Yudha

    2015-04-01

    Full Text Available The research was conducted based on the need for assistive devices for people to determine the location of the establishment of public refueling stations. Aids in the form of decision support systems. There are six criteria for determining the location of the establishment of broad land, land prices, traffic density, many transportation routes, distance to other retail outlets and administration. While the location is also six. In this study has successfully built a decision support system to determine the location of the establishment of public refueling stations using the method promethee. Hasi of this system of ranking based on the size of the leaving flow, entering flow, and net flow.

  5. Research on the penetration characteristic of supersonic molecule beam on the HL-1M tokamak

    International Nuclear Information System (INIS)

    Dong Jiafu; Luo Junling; Tang Nianyi; Li Wei; Zhong Yunze; Liu Yi; Fu Binzhong; Yao Lianghua; Feng Baibing; Qin Yunwen

    2002-01-01

    In the HL-1M plasma experiments, two refueling ways, the pellet injection and the gas puffing, are usually used. In recent years, a new refueling method, the supersonic molecular beam (SMB) injection, has been developed. In this paper, the penetration characteristics of SMB has been analyzed and researched. The SMB experiments were analyzed with H α emissivity measurement. The H α emissivity distribution in the plasma was calculated from multi-channel chord emission singles by means of the asymmetry Abel inversion method

  6. A generalized perturbation program for CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Yang, Won Sik [Chosun University, Kwangju (Korea, Republic of)

    1998-12-31

    A generalized perturbation program has been developed for the purpose of estimating zonal power variation of a CANDU reactor upon refueling operation. The forward and adjoint calculation modules of RFSP code were used to construct the generalized perturbation program. The numerical algorithm for the generalized adjoint flux calculation was verified by comparing the zone power estimates upon refueling with those of forward calculation. It was, however, noticed that the truncation error from the iteration process of the generalized adjoint flux is not negligible. 2 refs., 1 figs., 1 tab. (Author)

  7. 24-month fuel cycles

    International Nuclear Information System (INIS)

    Rosenstein, R.G.; Sipes, D.E.; Beall, R.H.; Donovan, E.J.

    1986-01-01

    Twenty-four month reload cycles can potentially lessen total power generation costs. While 24-month cores increase purchased fuel costs, the longer cycles reduce the number of refueling outages and thus enhance plant availability; men-rem exposure to site personnel and other costs associated with reload core design and licensing are also reduced. At dual unit sites an operational advantage can be realized by refueling each plant alternately on a 1-year offset basis. This results in a single outage per site per year which can be scheduled for off-peak periods or when replacement power costs are low

  8. Solid hydrogen-plasma interaction

    International Nuclear Information System (INIS)

    Joergensen, L.W.

    1976-03-01

    A review of the need of refuelling fusion reactors and of the possible refuelling methods, in particular injection of pellets of solid hydrogen isotopes, is given. The interaction between hydrogen pellets and a fusion plasma is investigated and a theoretical model is given. From this it is seen that the necessary injected speed is above 10 4 m/sec. Experiments in which hydrogen pellets are interacting with a rotating test plasma (puffatron plasma) is described. The experimental results partly verify the basic ideas of the theoretical model. (Auth.)

  9. Peach Bottom Atomic Power Station, Units 2 and 3. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Unit 2 experienced 11 forced outages, 5 power reductions, and one major refueling outage which lasted about 3 months during which time the feedwater spargers were replaced. Net electrical power generated was 5,569,633 MWH with the generator on line 5,998 hrs. Unit 3 experienced 17 forced outages, 11 power reductions and 2 major outages. The first refueling outage began 12/24/77. Net electrical power generated was 6,049,644 MWH with the unit on line 6,829 hrs. Information is presented concerning operations, personnel exposures, radioactive releases, maintenance, and irradiated fuel examination

  10. Clean Cities Award Winning Coalition: Coachella Valley

    Energy Technology Data Exchange (ETDEWEB)

    ICF Kaiser

    1999-05-20

    Southern California's Coachella Valley became a Clean Cities region in 1996. Since then, they've made great strides. SunLine Transit, the regional public transit provider, was the first transit provider to replace its entire fleet with compressed natural gas buses. They've also built the foundation for a nationally recognized model in the clean air movement, by partnering with Southern California Gas Company to install a refueling station and developing a curriculum for AFV maintenance with the College of the Desert. Today the valley is home to more than 275 AFVs and 15 refueling stations.

  11. Reliability assessment of the fueling machine of the CANDU reactor

    International Nuclear Information System (INIS)

    Al-Kusayer, T.A.

    1985-01-01

    Fueling of CANDU-reactors is carried out by two fueling machines, each serving one end of the reactor. The fueling machine becomes a part of the primary heat transport system during the refueling operations, and hence, some refueling machine malfunctions could result in a small scale-loss-of-coolant accident. Fueling machine failures and the failure sequences are discussed. The unavailability of the fueling machine is estimated by using fault tree analysis. The probability of mechanical failure of the fueling machine interface is estimated as 1.08 x 10 -5 . (orig.) [de

  12. Selection of LWR cycle length and fuel reload fraction

    International Nuclear Information System (INIS)

    Driscoll, M.J.; Handwerk, C.S.; McMahon, M.V.

    1997-01-01

    The continuing evolution of fuel having ever higher burnup capability and the increased emphasis on high plant capacity factor to keep nuclear power cost-competitive, motivates re-examination of some basic fuel management strategies. Specifically, what are the economic optimum goals for the fraction of core to be refueled, 1/n, and the length of the intra-refueling cycle, T c . The authors present a simple model to study these questions. They conclude that unless substantial improvements in technology are forthcoming, or economic circumstances change significantly, departure from 2- to 4-batch management, or longer than 2- to 3-year cycles in LWRs is not supported by their analysis

  13. Control of sawteeth and neo-classical tearing modes in tokamaks using electron cyclotron waves

    NARCIS (Netherlands)

    Baar, M.R. de; Bongers, W.A.; Berkel, M. van; Doelman, N.J.; Hennen, B.A.; Nuij, P.; Oosterbeek, J.W.; Steinbuch, M.; Westerhof, E.; Witvoet, G.

    2011-01-01

    Resistive magneto-hydrodynamic instabilities are expected to limit the performance of nuclear fusion reactors. Prime examples are the sawtooth instability and the neoclassical tearing modes. The sawtooth instability will affect the refueling of the plasma core and the fast particle concentration. In

  14. Research Article Special Issue

    African Journals Online (AJOL)

    2017-09-10

    Sep 10, 2017 ... The characteristic of near-space region is that its atmosphere is ... to land and refuel would be much better as a pseudo-satellite ... radar would not be affected by any cloud layer in the troposphere ...... performance for life cycle modeling in early stage design. ... Solar variability and its effects on climate.

  15. Irradiated fuel bundle counter

    International Nuclear Information System (INIS)

    Campbell, J.W.; Todd, J.L.

    1975-01-01

    The design of a prototype safeguards instrument for determining the number of irradiated fuel assemblies leaving an on-power refueled reactor is described. Design details include radiation detection techniques, data processing and display, unattended operation capabilities and data security methods. Development and operating history of the bundle counter is reported. (U.S.)

  16. Combined fuel assembly and thimble plug gripper for a nuclear reactor

    International Nuclear Information System (INIS)

    1977-01-01

    This invention relates to an apparatus for loading and unloading a fuel assembly into and from the core of a nuclear reactor and for removing and inserting control rod guide thimble plugs from and into the fuel assembly during a reactor refueling operation in substantially less time than that presently required and in a more reliable, safe and efficient manner. (UK)

  17. 40 CFR 86.098-2 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... 1985 and Later Model Year New Gasoline Fueled, Natural Gas-Fueled, Liquefied Petroleum Gas-Fueled and... on liquefied petroleum gas-fueled vehicles which uses a relatively small positive shutoff valve and... the fuel being dispensed into the tank of the test vehicle during a refueling test. Evaporative...

  18. A Theoretical Secure Enterprise Architecture for Multi Revenue Generating Smart Grid Sub Electric Infrastructure

    Science.gov (United States)

    Chaudhry, Hina

    2013-01-01

    This study is a part of the smart grid initiative providing electric vehicle charging infrastructure. It is a refueling structure, an energy generating photovoltaic system and charge point electric vehicle charging station. The system will utilize advanced design and technology allowing electricity to flow from the site's normal electric service…

  19. 78 FR 34966 - Approval and Promulgation of Air Quality Implementation Plans; Wisconsin; Removal of Gasoline...

    Science.gov (United States)

    2013-06-11

    ... Promulgation of Air Quality Implementation Plans; Wisconsin; Removal of Gasoline Vapor Recovery From Southeast... specifically installed at gasoline dispensing facilities (GDF) and capture the refueling fuel vapors at the gasoline pump nozzle. The system carries the vapors back to the underground storage tank at the GDF to...

  20. H. B. Robinson Plant, Unit 2. Semiannual operating report No. 11, July--December 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 2,119,115 MW(e) with the generator on line 3,308 hrs. Information is presented concerning operation, power generation, shutdowns, corrective maintenance, occupational radiation exposure, release of radioactive materials, tests, inspections, refueling, and steam generator outage

  1. Fast flux test facility final safety analysis report amendment 79

    International Nuclear Information System (INIS)

    Dautel, W.A.

    1999-01-01

    This document is provided to replace, remove, or add applicable pages to the chapters on: Heat Transport System; Containment and Structures; Auxiliary Systems; Reactor Refueling System; Conduct of Operations; Safety Analysis; Quality Assurance; FFTF Criticality Specifications; and Appendix H's TRIGA Fuel Storage System

  2. 24 Annual meeting of the Spanish Nuclear Society: Valladolid 14-16 October 1998: program and synopsis of lectures

    International Nuclear Information System (INIS)

    1998-01-01

    The technical sessions of XXIV annual meeting of the Spanish Nuclear Society were: 1) Fusion 2) Engineering: calculation and simulation. 3) Economical, legal and social aspect 4) Plant life extension 5) Operating experiences, refueling and operation support 6) Probabilistic safety 7) Radiological protection 8) Waste Management 9) Maintenance 10) Nuclear Safety R and D 11) Environmental aspects 12) Fuel 13) Quality

  3. Irradiated fuel bundle counter

    International Nuclear Information System (INIS)

    Campbell, J.W.; Todd, J.L.

    1975-01-01

    The design of a prototype safeguards instrument for determining the number of irradiated fuel assemblies leaving an on-power refueled reactor is described. Design details include radiation detection techniques, data processing and display, unattended operation capabilities and data security methods. Development and operating history of the bundle counter is reported

  4. Plant availability design aspects of Korean next generation reactor

    International Nuclear Information System (INIS)

    Woo Sang Lim; Ha Chung Beak

    1998-01-01

    The purpose of this paper is to describe the KNGR design concepts adopted for reducing forced outages and refueling outages, and current design changes, to assess their availability impacts compared to existing domestic nuclear power plants, and then to identify design directions for next design stage. (author)

  5. Nuclear reactor with makeup water assist from residual heat removal system

    Science.gov (United States)

    Corletti, M.M.; Schulz, T.L.

    1993-12-07

    A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path. 2 figures.

  6. The Goldwater Nichols Act of 1986: 30 Years of Acquisition Reform

    Science.gov (United States)

    2016-12-01

    helicopters failed to arrive at Desert One, the mission was aborted . While one helicopter was repositioning to a refuel point, it crashed into a C-130...unnecessary requirements and certifications,” another section 800 panel review to identify unnecessary acquisition legal requirements, and a study into the

  7. The U.S. Navy, the Neutrality Patrol, and Atlantic Fleet Escort Operations, 1939-1941

    Science.gov (United States)

    1991-05-13

    Hereward in the Yucatan Channel, watching as the British ship refueled from a G- 3 class cruiser.3 3 Later that month, two American destroyers and the...4 0 On 14 December, the German freighter Arauca put out of Veracruz, and shaped a course for Hamburg. The ship’s cargo included " sisal , phosphate

  8. Methods and techniques of nuclear in-core fuel management

    International Nuclear Information System (INIS)

    Jong, A.J. de.

    1992-04-01

    Review of methods of nuclear in-core fuel management (the minimal critical mass problem, minimal power peaking) and calculational techniques: reactorphysical calculations (point reactivity models, continuous refueling, empirical methods, depletion perturbation theory, nodal computer programs); optimization techniques (stochastic search, linear programming, heuristic parameter optimization). (orig./HP)

  9. The UK commercial demonstration fast reactor design

    International Nuclear Information System (INIS)

    Holmes, J.A.G.

    1987-01-01

    The paper on the UK Commercial Demonstration Fast Reactor design was presented to the seminar on 'European Commercial Fast Reactor Programme, London 1987. The design is discussed under the topic headings:- primary circuit, intermediate heat exchangers and pumps, fuel and core, refuelling, steam generators, and nuclear island layout. (U.K.)

  10. Quality planning for major plant design modifications

    International Nuclear Information System (INIS)

    Dulee, R.J.

    1988-01-01

    This paper reviews the approach and activities undertaken by Public Service Electric and Gas Company's (PSE and G's) nuclear quality assurance (QA) department to support major plant design modifications conducted during refueling outages at Salem Generating Station. It includes the planning and implementation of quality plans developed to provide both QA and quality control (QC) coverage of modification performed by contracted service organizations

  11. ASDEX papers at the 13th European conference on controlled fusion and plasma physics

    International Nuclear Information System (INIS)

    1986-05-01

    This report provides 29 ASDEX papers concerning pellet refuelling, confinement, high-beta plasma and MHD-equilibrium, heating by ICR, lower hybrid and current-drive, impurity studies and plasma diagnostics. All of these papers have been indexed separately. (GG)

  12. Flywheel-Based Distributed Bus Signalling Strategy for the Public Fast Charging Station

    DEFF Research Database (Denmark)

    Dragicevic, Tomislav; Sucic, Stepjan; Vasquez, Juan Carlos

    2014-01-01

    Fast charging stations (FCS) are able to recharge plug-in hybrid electric vehicles (pHEVs) in less than half an hour, thus representing an appealing concept to vehicle owners since the off-road time is similar as for refuelling at conventional public gas stations. However, since these FCS plugs...

  13. Technical specifications, La Salle County Station, Unit No. 1. Appendix A to License No. NPF-11, Docket No. 50-373

    International Nuclear Information System (INIS)

    1982-04-01

    Specifications are presented concerning safety limits; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; radiological environmental monitoring; reactor site; fuel storage; and plant operations

  14. 40 CFR 86.1834-01 - Allowable maintenance.

    Science.gov (United States)

    2010-07-01

    ... and coolers. (iv) For light-duty trucks, light-duty vehicles, and complete heavy-duty vehicles, the adjustment, cleaning, repair, or replacement of the oxygen sensor shall occur at 80,000 miles (or 2,400 hours... sensors (except oxygen sensor) and actuators. (E) Evaporative and/or refueling emission canister(s). (F...

  15. The Palm Desert renewable [hydrogen] transportation system

    Energy Technology Data Exchange (ETDEWEB)

    Chamberlin, C.E.; Lehman, P. [Humboldt State Univ., Arcata, CA (United States). Schatz Energy Research Center

    1998-08-01

    This paper describes the Schatz Energy Research Center (SERC) progress on the Palm Desert Renewable Hydrogen Transportation System Project for the period June 1997 through May 1998. The project began in March 1996. The goal of the Palm Desert Project is to develop a clean and sustainable transportation system for a community. The project demonstrates the practical utility of hydrogen as a transportation fuel and the proton exchange membrane (PEM) fuel cell as a vehicle power system. The project includes designing and building 4 fuel cell powered vehicles, a solar hydrogen generating and refueling station, and a fuel cell vehicle diagnostic center. Over this last year, SERC has built a fuel cell powered neighborhood electric vehicle and delivered it to the City of Palm Desert. The design of the hydrogen refueling station is near completion and it is anticipated that construction will be complete in the fall of 1998. The vehicles are currently being refueled at a temporary refueling station. The diagnostic center is being designed and maintenance procedures as well as computer diagnostic programs for the fuel cell vehicles are being developed. City employees are driving the vehicles daily and monitoring data are being collected. The drivers are pleased with the performance of the vehicles.

  16. Technical specifications: River Bend Station (Docket No. 50-458). Appendix ''A'' to License No. NPF-40

    International Nuclear Information System (INIS)

    1985-08-01

    Limiting conditions for operation and surveillance requirements are presented for the reactvity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; and radiological environmental monitoring

  17. U.S. - UK - Canada Trilateral Symposium

    Science.gov (United States)

    2009-10-02

    e . 4. Procedures for intra-community arms transfers simplified. 5 Retransfer controls disco raged b t m st be. u u u complied with. Li d...IRIS – T • Airbus A310 refueller 10 FUTURE OF TRANSATLANTIC ARMAMENTS COOPERATION 1996 VISION – “I believe that national security – ours and that

  18. Assessment of DoD-Provided Healthcare for Members of the United States Armed Forces Reserve Components

    Science.gov (United States)

    2014-10-08

    Force Base, Texas • Air National Guard Combat Readiness Training Center, Alpena, Michigan • 113th Air Support Operations Squadron, Terre Haute...Wing, Terre Haute, Indiana • 185th Air Refueling Wing, Sioux City, Iowa • 349 Air Mobility Wing, Travis Air Force Base, California • 434 Air

  19. 48 CFR 217.171 - Multiyear contracts for services.

    Science.gov (United States)

    2010-10-01

    ... services (e.g., ground maintenance, in-plane refueling, bus transportation, and refuse collection and... installation being closed or realigned under a base closure law as defined in 10 U.S.C. 2667(h)(2); or (C) A... Public Law 105-56 and similar sections in subsequent DoD appropriations acts); or (ii) A cancellation...

  20. Nuclear reactor with makeup water assist from residual heat removal system

    Science.gov (United States)

    Corletti, Michael M.; Schulz, Terry L.

    1993-01-01

    A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path.

  1. Nuclear reactor with makeup water assist from residual heat removal system

    International Nuclear Information System (INIS)

    Corletti, M.M.; Schulz, T.L.

    1993-01-01

    A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path. 2 figures

  2. Dresden 1 Plutonium Recycle Program report for the period July 1, 1975--December 31, 1975

    International Nuclear Information System (INIS)

    Wan, M.Y.

    1976-07-01

    Included are a summary of reactor operations, power and exposure histories for each mixed-oxide assembly, 4 reports on the fuel inspections which were performed during the Cycle 8 refueling outage, and plans and schedules for the remainder of the program

  3. CANDU-6 fuel optimization for advanced cycles

    Energy Technology Data Exchange (ETDEWEB)

    St-Aubin, Emmanuel, E-mail: emmanuel.st-aubin@polymtl.ca; Marleau, Guy, E-mail: guy.marleau@polymtl.ca

    2015-11-15

    Highlights: • New fuel selection process proposed for advanced CANDU cycles. • Full core time-average CANDU modeling with independent refueling and burnup zones. • New time-average fuel optimization method used for discrete on-power refueling. • Performance metrics evaluated for thorium-uranium and thorium-DUPIC cycles. - Abstract: We implement a selection process based on DRAGON and DONJON simulations to identify interesting thorium fuel cycles driven by low-enriched uranium or DUPIC dioxide fuels for CANDU-6 reactors. We also develop a fuel management optimization method based on the physics of discrete on-power refueling and the time-average approach to maximize the economical advantages of the candidates that have been pre-selected using a corrected infinite lattice model. Credible instantaneous states are also defined using a channel age model and simulated to quantify the hot spots amplitude and the departure from criticality with fixed reactivity devices. For the most promising fuels identified using coarse models, optimized 2D cell and 3D reactivity device supercell DRAGON models are then used to generate accurate reactor databases at low computational cost. The application of the selection process to different cycles demonstrates the efficiency of our procedure in identifying the most interesting fuel compositions and refueling options for a CANDU reactor. The results show that using our optimization method one can obtain fuels that achieve a high average exit burnup while respecting the reference cycle safety limits.

  4. A feasibility study on the longer cycle operation of Yonggwang nuclear power plants 3 and 4 NSSS design

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Young Joon; Choi, Hae Yoon; Chang, Young Woo [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)] [and others

    1996-06-01

    A feasible study on the NSSS design safety assessment is performed for a longer cycle operation of Yonggang units 3 and 4. The analysis of the drift errors increased and setting point changed for safety related instrument channels due to the longer refueling interval was done to assess the impact on the operational safety performance and availability of the plant if the refueling interval was extended. In the result of LOCA analysis, even though the Peak Cladding Temperature (PCT) is slightly increased due to Pin/Box ratio decrease, the PCT has enough margin and, therefore, it was proven to be acceptable. From the perspective of return-to-power and the pre-trip fuel performance during the transient operation, an impact on the results of an SLB accident analysis were assessed. The overall trend of the longer refueling operation of 18 months is similar to the standard refuel operation of 12 months. The possibility of the return to power during SLB accident condition was estimated, the detailed analysis of the reactor core using the 3-dimensional model methodology is required to confirm the fuel integrity. 11 refs.(Author) .new.

  5. Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 1 (Docket No. 50-528). Appendix A to License No. NPF-34

    International Nuclear Information System (INIS)

    1984-12-01

    Technical specifications are presented concerning operating safety limits for reactivity control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring; design features of the reactor site, containment, reactor core, coolant system, and fuel storage; and administrative controls

  6. Technical Specifications: Palo Verde Nuclear Generating Station, Unit No. 1 (Docket No. 50-528). Appendix ''A'' to License No. NPF-41

    International Nuclear Information System (INIS)

    1985-05-01

    Information on the limiting conditions for operation is presented concerning reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, and radiological environmental monitoring

  7. Supply reliability and dynamic safety analysis of an alternative energy supply chain

    DEFF Research Database (Denmark)

    Herbert-Hansen, Zaza Nadja Lee; Markert, Frank; Jacobsen, Peter

    2016-01-01

    This paper focuses on the integration of risk and supply chain modelling by means of analysing a case concerning a Hydrogen Refuelling Station in Berlin. It presents a framework that can analyse an energy supply chain and at the same time enables easy reporting and presentation of various results...

  8. TACOM LCMC Industrial Base Engineering Support - Board of Directors

    Science.gov (United States)

    2011-07-01

    Hex Chrome Replacement (High Purity Aluminum) Capability o Advanced Aviation Forward Area Refueling System (AAFARS)Tech Data Development o Common...SIAD (As needed) Example Issues: • Hexavalent Chromium/Cadmium (RRAD) • Common Adhesive (ANAD) • AVLB Pressure Plate (ANAD) • Paladin Corrosion

  9. Equilibrium core layout for the 1000 MW direct cycle HTR (HHT) with hexagonal monolith moulded fuel blocks

    Energy Technology Data Exchange (ETDEWEB)

    Dworak, A

    1973-03-15

    The aim of this survey is to calculate an equilibrium Thorium fuel cycle for a 1000 MW HHT-core in off-load refuelling with hexagonal monolith moulded fuel blocks. It was tried to achieve an axial power distribution similar to the advanced pebble-bed reactors (OTTO) by introducing three axial core zones with different heavy metal content and initial enrichment.

  10. Knowledge Management Integration into Strategic Human Capital Management Systems

    International Nuclear Information System (INIS)

    Marco, Tony; Heler, David

    2014-01-01

    Leadership model philosophies: • Knowledge is fundamental – share it; • We are in the refueling outage business; • Cost effective does not necessarily mean cheap; • Working efficiently and event free; • Make conscious, informed decisions; • Excellence in Operational Focus; • Operations Leads the Station; • End of Licenses and Beyond 60; • Our Leadership Model - Our future

  11. LARA: Expert system for acoustic localization of robot in a LMFBR

    International Nuclear Information System (INIS)

    Lhuillier, C.; Malvache, P.

    1986-12-01

    The expert system LARA (Acoustic Localization of Autonomic Robot) has been developed to show the interest of introducing artificial intelligency for fine automatic positioning of refuelling machine in a LMFBR reactor. LARA which is equipped with an acoustic detector gives rapidly a good positioning on the fuel [fr

  12. Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

    International Nuclear Information System (INIS)

    Anderson, F.D.

    1984-06-01

    Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

  13. RA Reactor operation and maintenance (I-IX), Part I; Pogon i odrzavanje reaktora RA (I-IX), I Deo

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    The report on RA reactor operation and maintenance for year 1963 is divided in six tasks. This volume contains the introductory report, and three tasks of the final report, namely reactor exploitation, reactivity changes of the RA reactor before repair, planning of refuelling.

  14. 76 FR 80832 - Fire Pots and Gel Fuel; Advance Notice of Proposed Rulemaking; Request for Comments and Information

    Science.gov (United States)

    2011-12-27

    ... also have marketed their own brands of gel fuel. The leading firms in the firepot market have fewer..., the 25- year-old victim reported: ``We poured (brand X) fuel gel into our fire pot and lit it. We sat... increase consumers' awareness of the presence of a flame. To address the refueling hazard, one option may...

  15. Technical specifications: Grand Gulf Nuclear Station, Unit No. 1. Docket No. 50-416, Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1982-06-01

    Technical specifications are presented concerning safety limits; limiting safety system settings; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; site; and administrative controls

  16. Skipping swans : Fuelling rates and wind conditions determine differential use of migratory stopover sites of Bewick's Swans Cygnus bewickii

    NARCIS (Netherlands)

    Beekman, JH; Nolet, BA; Klaassen, M

    2002-01-01

    Some migratory birds refuel at stopover sites that they by-pass on the return trip. In theory, this skipping behaviour is only expected in time-selected migrants when the overflown site is of a lower quality than the departure site. We provide empirical evidence that quality differences in stopover

  17. Skipping swans: Fuelling rates and wind conditions determine differential use of migratory stopover sites of Bewick's Swans Cygnus bewickii

    NARCIS (Netherlands)

    Beekman, J.H.; Nolet, B.A.; Klaassen, M.R.J.

    2002-01-01

    Some migratory birds refuel at stopover sites that they by-pass on the return trip. In theory, this skipping behaviour is only expected in time-selected migrants when the overflown site is of a lower quality than the departure site. We provide empirical evidence that quality differences in stopover

  18. Economic design in a long-distance migrating molluscivore: how fast-fuelling red knots in Bohai Bay, China, get away with small gizzards

    NARCIS (Netherlands)

    Yang, H.-Y.; Ma, Z.-J.; Hua, N.; van Gils, J.A.; Zhang, Z.-W.; Piersma, T.

    2013-01-01

    We carried out an observational and experimental study to decipher how resource characteristics, in interaction with the predator's phenotype, constrain a fitness-determining performance measure, i.e. refuelling in a migrant bird. Two subspecies of red knot (Calidris canutus rogersi and C. c.

  19. Millstone Nuclear Power Station, Unit 1. Annual operating report: 1 January--31 December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical power generated was 3,752,445 MWh with the generator on line 6,682 hrs. Information is presented concerning operations; shutdowns and power reductions; refueling; maintenance; failed fuel elements; power generation; occupational personnel radiation exposure; and changes in technical specifications, plant design, and key supervisory personnel

  20. 76 FR 61062 - Approval and Promulgation of Implementation Plans; Arizona; Update to Stage II Gasoline Vapor...

    Science.gov (United States)

    2011-10-03

    ... the second is the fueling for race cars during the racing event. According to the information provided... facility's fixed gasoline dispensers, which are used to fuel service vehicles, are not used for race car... raceway exemption as it applies to refueling of race cars, which are not designed for street or highway...

  1. 75 FR 20627 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-04-20

    ... replacement SGs, their method of operation, operational leakage limits, or primary coolant chemistry controls... Instrumentation,'' Table 3.3.5-1, to raise the refueling water tank (RWT) low level allowable values for the... of the Chemical and Volume Control System (CVCS) that supports ECCS [emergency core cooling system...

  2. Intake rates, stochasticity, or onset of spring – what aspects of food availability affect spring migration patterns in Pink-footed Geese Anser brachyrhynchus?

    NARCIS (Netherlands)

    Bauer, S.; Madsen, J.; Klaassen, M.R.J.

    2006-01-01

    Long-distance bird migration consists of several flight episodes interrupted by a series of resting and refuelling periods on stopover sites. We assessed the role of food availability as the determinant of staging decisions focusing on the following three aspects of food availability: intake rates,

  3. Experimental validation of Pu-Sm evolution model for CANDU-6 power transients

    International Nuclear Information System (INIS)

    Coutsiers, Eduardo E.; Pomerantz, Marcelo E.; Moreno, Carlos A.

    2000-01-01

    Development of a methodology to evaluate the reactivity produced by Pu-Sm transient, effect displayed after power transients. This methodology allows to predict the behavior of liquid zones with which the fine control of CANDU reactor power is made. With this information, it is easier to foresee the refueling demand after power movements. The comparison with experimental results showed good agreement. (author)

  4. Technical specifications: Diablo Canyon Nuclear Power Plant, Unit No. 2 (Docket No. 50-323). Appendix ''A'' to License No. DPR-81

    International Nuclear Information System (INIS)

    1985-04-01

    Information is presented concerning the limiting conditions for operation for the reactivity control systems, instrumentation, power distribution limits, reactor coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, and radiological environmental monitoring

  5. Technical specifications: Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1985-08-01

    Safety limits and limiting safety system settings are presented for the reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; and radiological environmental monitoring

  6. 75 FR 34701 - Procurement List; Proposed Additions

    Science.gov (United States)

    2010-06-18

    ...--Scissors, Ladies Sewing; Stainless Steel Coverage: A-List for the Total Government Requirement as... SERVICE, GSA/FSS TOOLS ACQUISITION DIVISION I, KANSAS CITY, MO. Services Service Type/Location: Mess Attendant Service, 185th Air Refueling Wing Dining Hall, 2920 Headquarters Avenue, Sioux City, IA. NPA...

  7. RAPID-L Highly Automated Fast Reactor Concept Without Any Control Rods (1) Reactor concept and plant dynamics analyses

    International Nuclear Information System (INIS)

    Kambe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Iwamura, Takamichi

    2002-01-01

    The 200 kWe uranium-nitride fueled lithium cooled fast reactor concept 'RAPID-L' to achieve highly automated reactor operation has been demonstrated. RAPID-L is designed for Lunar base power system. It is one of the variants of RAPID (Refueling by All Pins Integrated Design), fast reactor concept, which enable quick and simplified refueling. The essential feature of RAPID concept is that the reactor core consists of an integrated fuel assembly instead of conventional fuel subassemblies. In this small size reactor core, 2700 fuel pins are integrated altogether and encased in a fuel cartridge. Refueling is conducted by replacing a fuel cartridge. The reactor can be operated without refueling for up to 10 years. Unique challenges in reactivity control systems design have been attempted in RAPID-L concept. The reactor has no control rod, but involves the following innovative reactivity control systems: Lithium Expansion Modules (LEM) for inherent reactivity feedback, Lithium Injection Modules (LIM) for inherent ultimate shutdown, and Lithium Release Modules (LRM) for automated reactor startup. All these systems adopt lithium-6 as a liquid poison instead of B 4 C rods. In combination with LEMs, LIMs and LRMs, RAPID-L can be operated without operator. This is the first reactor concept ever established in the world. This reactor concept is also applicable to the terrestrial fast reactors. In this paper, RAPID-L reactor concept and its transient characteristics are presented. (authors)

  8. Fulltext PDF

    Indian Academy of Sciences (India)

    1Refueling Technology Division, Bhabha Atomic Research Centre, Mumbai 400 085, India. 2Computational ... at the atomistic scales for crystal copper (Cu) has the same qualitative behaviour as the DFRACT model, albeit ... tionally investigated by molecular dynamics which is well suited to study many millions of atoms for ...

  9. CANFLEX fuel bundle impact test

    International Nuclear Information System (INIS)

    Chang, Seok Kyu; Chung, C. H.; Park, J. S.; Hong, S. D.; Kim, B. D.

    1997-08-01

    This document outlines the test results for the impact test of the CANFLEX fuel bundle. Impact test is performed to determine and verify the amount of general bundle shape distortion and defect of the pressure tube that may occur during refuelling. The test specification requires that the fuel bundles and the pressure tube retain their integrities after the impact test under the conservative conditions (10 stationary bundles with 31kg/s flow rate) considering the pressure tube creep. The refuelling simulator operating with pneumatic force and simulated shield plug were fabricated and the velocity/displacement transducer and the high speed camera were also used in this test. The characteristics of the moving bundle (velocity, displacement, impacting force) were measured and analyzed with the impact sensor and the high speed camera system. The important test procedures and measurement results were discussed as follows. 1) Test bundle measurements and the pressure tube inspections 2) Simulated shield plug, outlet flange installation and bundle loading 3) refuelling simulator, inlet flange installation and sensors, high speed camera installation 4) Perform the impact test with operating the refuelling simulator and measure the dynamic characteristics 5) Inspections of the fuel bundles and the pressure tube. (author). 8 refs., 23 tabs., 13 figs

  10. Haddam Neck Plant. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Gross electrical power generated was 2,464,308 MWh(e) with the reactor on line 4,417 hrs. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, primary coolant chemistry, occupational radiation exposure, release of radioactive materials, reportable occurrences, changes in plant, technical specifications, core vi start-up, containment leak testing, and core v and vi refueling

  11. Navy John Lewis (TAO 205) Class Oiler Shipbuilding Program: Background and Issues for Congress

    Science.gov (United States)

    2016-08-18

    These wires are placed under tension to support fuel hoses for refueling operations or trolleys that move pallets of provisions, ammunition, or other...SECNAV Mabus Names First TAO(X) Next Generation Oiler After Rep. John Lewis,” USNI News, January 6, 2016. 6 Sam LaGrone, “Navy to Name Ship After Gay

  12. 40 CFR 112.6 - Qualified Facilities Plan Requirements.

    Science.gov (United States)

    2010-07-01

    ... locate mobile or portable oil storage containers to prevent a discharge as described in § 112.1(b). (iii...). Construct all bulk storage container installations (except mobile refuelers and other non-transportation-related tank trucks), including mobile or portable oil storage containers, so that you provide a secondary...

  13. Alternative Fuels Data Center: Publications

    Science.gov (United States)

    refueling infrastructure. Waste-to-Fuel: A Case Study of Converting Food Waste to Renewable Natural Gas as a 5,300 PEVs on the road by the end of 2019. This analysis finds that while consumer demand for fast vehicles), a minimum level of fast charging coverage across the city is required to ease consumer range

  14. Devices for the contamination containment employees in the steam generator inspection; Dispositivo para confinamiento de la contaminacion empleados en la inspeccion de generadores de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Bueno, A.; Largo Izquierdo, P.; Calleja Rubio, J. A.

    2010-07-01

    The process of induced current inspection of the tubes of the steam generator is a typical programmed inspections at each refueling outages of pressurized water in nuclear power plants. components inspection being quite active, interested in the program of continuous improvement, further optimize the inspection system.

  15. Brunswick Steam Electric Plant, Units 1 and 2. Annual operating report No. 3

    International Nuclear Information System (INIS)

    1977-01-01

    After a month-by-month summary of operations and maintenance activities, data are presented concerning modifications, procedure changes, and man-rem radiation doses. Appendices include information on the main generator outage, leak rate testing, refueling outage, recirculation pump modifications, and instrument drift

  16. 76 FR 39136 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-07-05

    ... the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR part 2. Interested... Generator (SG) Program,'' to exclude a portion of the tubes below the top of the steam generator tubesheet from periodic steam generator tube inspections during Refueling Outage 14 and the subsequent operating...

  17. 40 CFR 112.8 - Spill Prevention, Control, and Countermeasure Plan requirements for onshore facilities (excluding...

    Science.gov (United States)

    2010-07-01

    ... exhaust lines through a settling tank, skimmer, or other separation or retention system. (8) Engineer or... located outside containment walls or where tank truck discharges may occur outside the loading area) to.... (2) Construct all bulk storage tank installations (except mobile refuelers and other non...

  18. 30 CFR 56.4103 - Fueling internal combustion engines.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fueling internal combustion engines. 56.4103... Prevention and Control Prohibitions/precautions/housekeeping § 56.4103 Fueling internal combustion engines. Internal combustion engines shall be switched off before refueling if the fuel tanks are integral parts of...

  19. 30 CFR 57.4103 - Fueling internal combustion engines.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fueling internal combustion engines. 57.4103... Prevention and Control Prohibitions/precautions/housekeeping § 57.4103 Fueling internal combustion engines. Internal combustion engines shall be switched off before refueling if the fuel tanks are integral parts of...

  20. Fuel Cycle Cost Calculations for a 120,000 shp PWR for Ship Propulsion. RCN Report

    International Nuclear Information System (INIS)

    Dekker, N.H.; Foggi, C.; Giacomazzi, G.

    1972-02-01

    A parametric study of the fuel cycle costs for a 120,000 SHP PWR for ship propulsion has been carried out. Variable parameters are: fuel pellet diameter, moderating ratio and refuelling scheme. Minimum fuel cycle costs can be obtained at moderating ratios of about 2.2. Both fuel cycle costs and reactor control requirements favour the two batch core. (author)