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Sample records for iter maintenance operations

  1. Applying principles of Design For Assembly to ITER maintenance operations

    International Nuclear Information System (INIS)

    Heemskerk, Cock; de Baar, Marco; Elzendoorn, Ben; Koning, Jarich; Verhoeven, Toon; Vreede, Fred de

    2009-01-01

    In ITER, maintenance operations in the vessel and in the Hot Cell will be largely done by Remote Handling (RH). Remotely performed maintenance actions tend to be more time-costly than actions performed by direct human access. With a human operator in the control loop and adequate situational feedback, a two-armed master slave manipulator system can mimic direct access with dexterous manipulation, tactile feedback and vision. But even then, turnaround times are still very high. Adapting the design for simplified maintenance operations can yield significant time savings. One of the methods known to produce a simpler, more robust design, which is also better suited for handling with robots, is Design For Assembly (DFA). This paper discusses whether and how the principles of DFA can be applied to simplify maintenance operations for ITER. While DFA is normally used with series-production and ITER is a unique product, it is possible to apply the principles of DFA to ITER maintenance operations. Furthermore, DFA's principles can be applied at different abstraction levels. Combining principles of DFA with Virtual Reality leads to new insights and provides additional value.

  2. Remote maintenance development for ITER

    International Nuclear Information System (INIS)

    Tada, Eisuke; Shibanuma, Kiyoshi

    1998-01-01

    This paper describes the overall ITER remote maintenance design concept developed mainly for in-vessel components such as diverters and blankets, and outlines the ITER R and D program to develop remote handling equipment and radiation hard components. Reactor structures inside the ITER cryostat must be maintained remotely due to DT operation, making remote handling technology basic to reactor design. The overall maintenance scenario and design concepts have been developed, and maintenance design feasibility, including fabrication and testing of full-scale in-vessel remote maintenance handling equipment and tool, is being verified. (author)

  3. Remote maintenance development for ITER

    Energy Technology Data Exchange (ETDEWEB)

    Tada, Eisuke [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Shibanuma, Kiyoshi

    1998-04-01

    This paper describes the overall ITER remote maintenance design concept developed mainly for in-vessel components such as diverters and blankets, and outlines the ITER R and D program to develop remote handling equipment and radiation hard components. Reactor structures inside the ITER cryostat must be maintained remotely due to DT operation, making remote handling technology basic to reactor design. The overall maintenance scenario and design concepts have been developed, and maintenance design feasibility, including fabrication and testing of full-scale in-vessel remote maintenance handling equipment and tool, is being verified. (author)

  4. The ITER remote maintenance system

    International Nuclear Information System (INIS)

    Tesini, A.; Palmer, J.

    2008-01-01

    The aim of this paper is to summarize the ITER approach to machine components maintenance. A major objective of the ITER project is to demonstrate that a future power producing fusion device can be maintained effectively and offer practical levels of plant availability. During its operational lifetime, many systems of the ITER machine will require maintenance and modification; this can be achieved using remote handling methods. The need for timely, safe and effective remote operations on a machine as complex as ITER and within one of the world's most hostile remote handling environments represents a major challenge at every level of the ITER Project organization, engineering and technology. The basic principles of fusion reactor maintenance are presented. An updated description of the ITER remote maintenance system is provided. This includes the maintenance equipment used inside the vacuum vessel, inside the hot cell and the hot cell itself. The correlation between the functions of the remote handling equipment, of the hot cell and of the radwaste processing system is also described. The paper concludes that ITER has equipped itself with a good platform to tackle the challenges presented by its own maintenance and upgrade needs

  5. ITER assembly and maintenance

    International Nuclear Information System (INIS)

    Honda, T.; Davis, F.; Lousteau, D.

    1991-01-01

    This document is intended to describe the work conducted by the ITER Assembly and Maintenance (A and M) Design Unit and the supporting home teams during the ITER Conceptual Design Activities, carried out from 1988 through 1990. Its content consists of two main sections, i.e., Chapter III, which describes the identified tasks to be performed by the A and M system and a general description of the required equipment; and Chapter IV, which provides a more detailed description of the equipment proposed to perform the assigned tasks. A two-stage R and D program is now planned, i.e., (1) a prototype equipment functional tests using full scale mock-ups and (2) a full scale integration demonstration test facility with real components (vacuum vessel with ports, blanket modules, divertor modules, armor tiles, etc.). Crucial in-vessel and ex-vessel operations and the associated remote handling equipment, including handling of divertor plates and blanket modules will be demonstrated in the first phase, whereby the database needed to proceed with the engineering phase will be acquired. The second phase will demonstrate the ability of the overall system to execute the required maintenance procedures and evaluate the performance of the prototype equipment

  6. Extending Virtual Reality simulation of ITER maintenance operations with dynamic effects

    International Nuclear Information System (INIS)

    Heemskerk, C.J.M.; Baar, M.R. de; Boessenkool, H.; Graafland, B.; Haye, M.J.; Koning, J.F.; Vahedi, M.; Visser, M.

    2011-01-01

    Virtual Reality (VR) simulation can be used to study, improve and verify ITER maintenance operations during preparation. VR can also improve the situational awareness of human operators during actual Remote Handling (RH) operations. Until now, VR systems use geometric models of the environment and the objects being handled and kinematic models of the manipulation systems. The addition of dynamic effects into the VR simulation was investigated. Important dynamic effects are forces due to contact transitions and the bending of beams under heavy loads. A novel dynamics simulation module was developed and introduced as an add-on to the VR4Robots VR software. Tests were performed under simplified test conditions and in the context of realistic ITER maintenance tasks on a benchmark product and on the ECRH Upper Port Launcher Plug (UPL). The introduction of dynamic effects into VR simulations was found to add realism and provide new insights in procedure development. The quality of the haptic feedback depends strongly on the haptic device used to 'display' haptic feedback to the operator. Dynamic effect simulation can also form the basis for real-time guidance support to operators during the execution of maintenance tasks (augmented reality).

  7. Remote maintenance development for ITER

    International Nuclear Information System (INIS)

    Tada, Eisuke; Shibanuma, Kiyoshi

    1997-01-01

    This paper both describes the overall design concept of the ITER remote maintenance system, which has been developed mainly for use with in-vessel components such as divertor and blanket, and outlines of the ITER R and D program, which has been established to develop remote handling equipment/tools and radiation hard components. In ITER, the reactor structures inside cryostat have to be maintained remotely because of activation due to DT operation. Therefore, remote-handling technology is fundamental, and the reactor-structure design must be made consistent with remote maintainability. The overall maintenance scenario and design concepts of the required remote handling equipment/tools have been developed according to their maintenance classification. Technologies are also being developed to verify the feasibility of the maintenance design and include fabrication and testing of a fullscale remote-handling equipment/tools for in-vessel maintenance. (author)

  8. Tritium and heat management in ITER Test Blanket Systems port cell for maintenance operations

    Energy Technology Data Exchange (ETDEWEB)

    Giancarli, L.M., E-mail: luciano.giancarli@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Cortes, P.; Iseli, M.; Lepetit, L.; Levesy, B. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Livingston, D. [Frazer-Nash Consultancy Ltd., Stonebridge House, Dorking Business Park, Dorking, Surrey RH4 1HJ (United Kingdom); Nevière, J.C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Pascal, R. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Ricapito, I. [Fusion for Energy, Josep Pla, 2, Torres Diagonal Litoral B3, Barcelona E-08019 (Spain); Shu, W. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Wyse, S. [Frazer-Nash Consultancy Ltd., Stonebridge House, Dorking Business Park, Dorking, Surrey RH4 1HJ (United Kingdom)

    2014-10-15

    Highlights: •The ITER TBM Program is one of the ITER missions. •We model a TBM port cell with CFD to optimize the design choices. •The heat and tritium releases management in TBM port cells has been optimized. •It is possible to reduce the T-concentration below one DAC in TBM port cells. •The TBM port cells can have human access within 12 h after shutdown. -- Abstract: Three ITER equatorial port cells are dedicated to the assessment of six different designs of breeding blankets, known as Test Blanket Modules (TBMs). Several high temperature components and pipework will be present in each TBM port cell and will release a significant quantity of heat that has to be extracted in order to avoid the ambient air and concrete wall temperatures to exceed allowable limits. Moreover, from these components and pipes, a fraction of the contained tritium permeates and/or leaks into the port cell. This paper describes the optimization of the heat extraction management during operation, and the tritium concentration control required for entry into the port cell to proceed with the required maintenance operations after the plasma shutdown.

  9. The ITER remote maintenance system

    International Nuclear Information System (INIS)

    Tesini, A.; Palmer, J.

    2007-01-01

    ITER is a joint international research and development project that aims to demonstrate the scientific and technological feasibility of fusion power. As soon as the plasma operation begins using tritium, the replacement of the vacuum vessel internal components will need to be done with remote handling techniques. To accomplish these operations ITER has equipped itself with a Remote Maintenance System; this includes the Remote Handling equipment set and the Hot Cell facility. Both need to work in a cooperative way, with the aim of minimizing the machine shutdown periods and to maximize the machine availability. The ITER Remote Handling equipment set is required to be available, robust, reliable and retrievable. The machine components, to be remotely handle-able, are required to be designed simply so as to ease their maintenance. The baseline ITER Remote Handling equipment is described. The ITER Hot Cell Facility is required to provide a controlled and shielded area for the execution of repair operations (carried out using dedicated remote handling equipment) on those activated components which need to be returned to service, inside the vacuum vessel. The Hot Cell provides also the equipment and space for the processing and temporary storage of the operational and decommissioning radwaste. A conceptual ITER Hot Cell Facility is described. (orig.)

  10. Remote handling maintenance of ITER

    International Nuclear Information System (INIS)

    Haange, R.

    1999-01-01

    The remote maintenance strategy and the associated component design of the International Thermonuclear Experimental Reactor (ITER) have reached a high degree of completeness, especially with respect to those components that are expected to require frequent or occasional remote maintenance. Large-scale test stands, to demonstrate the principle feasibility of the remote maintenance procedures and to develop the required equipment and tools, were operational at the end of the Engineering Design Activities (EDA) phase. The initial results are highly encouraging: major remote equipment deployment and component replacement operations have been successfully demonstrated. (author)

  11. Main maintenance operations for Test Blanket Systems in ITER TBM port cells

    Energy Technology Data Exchange (ETDEWEB)

    Pascal, R., E-mail: romain.pascal@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Cortes, P.; Friconneau, J.-P.; Giancarli, L.M.; Gotewal, K.K.; Iseli, M.; Kim, B.Y.; Levesy, B.; Martins, J.-P.; Merola, M. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Patisson, L. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Siarras, A. [Sogetti, Parc de la Duranne, 13857 Aix-en-Provence (France); Tesini, A. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

    2013-10-15

    Highlights: • The Test Blanket System components layout in Port Cell room is described. • The maintenance of the two Test Blanket Systems in ITER port cell is addressed. • The overall replacement/maintenance strategy is defined. • The main maintenance tasks of the systems are discussed. • The maintenance strategy and required tools are presented. -- Abstract: Each Test Blanket System in ITER is formed by an in-vessel component, the Test Blanket Module, and several associated ancillary systems (coolant and Tritium systems, instrumentation and control systems). The paper describes the overall replacement/maintenance strategy and the main maintenance tasks that have to be considered in the design of the systems. It shows that there are no critical issues.

  12. Design of an overhead crane for the ITER NB cell remote handling maintenance operations

    Energy Technology Data Exchange (ETDEWEB)

    Taubmann, Gonzalo; Brochet, Laurent [IBERTEF A.I.E., Iberica de Tecnologia de Fusion, C/Magallanes 3, 28015 Madrid (Spain); Liniers, Macarena [Asociacion EURATOM-CIEMAT para la Fusion, Av. Complutense 22, 28040 Madrid (Spain)], E-mail: macarena.liniers@ciemat.es; Medrano, Mercedes; Sarasola, Xabier; Botija, Jose; Alonso, Javier [Asociacion EURATOM-CIEMAT para la Fusion, Av. Complutense 22, 28040 Madrid (Spain); Damiani, Carlo [FUSION FOR ENERGY, Josep Pla 2, Torres Diagonal Litoral Ed B3, 08019 Barcelona (Spain)

    2009-06-15

    In the neutral beam cell of ITER all the maintenance operations on the neutral beam components (BLC's) must be performed by an overhead crane of large payload capability (30-50 tonnes). A crane system is presented consisting of a monorail, a carriage, and a lifting mechanism. The monorail must give access to the BLC's in the beam line vessel, the front components connecting the NB vessel with the Tokamak, and a storage area at the north end of the NB cell. Rail switching points are required at the intersections between radial and toroidal branches. A translational switching mechanism is proposed. The crane carriage consists of two independent sub-carriages, each composed of four wheels. A set of four secondary wheels attached to the main carriage prevents the crane tilting due to the CoG misalignment of some loads. The elevation system proposed consists of an electromechanical crane of four independent drums and 50 tonnes payload. In parallel with the crane design, a logistics and space availability study has been carried out, leading to the detection of clearance or transport problems that could be taken into account in the final crane design.

  13. Design of an overhead crane for the ITER NB cell remote handling maintenance operations

    International Nuclear Information System (INIS)

    Taubmann, Gonzalo; Brochet, Laurent; Liniers, Macarena; Medrano, Mercedes; Sarasola, Xabier; Botija, Jose; Alonso, Javier; Damiani, Carlo

    2009-01-01

    In the neutral beam cell of ITER all the maintenance operations on the neutral beam components (BLC's) must be performed by an overhead crane of large payload capability (30-50 tonnes). A crane system is presented consisting of a monorail, a carriage, and a lifting mechanism. The monorail must give access to the BLC's in the beam line vessel, the front components connecting the NB vessel with the Tokamak, and a storage area at the north end of the NB cell. Rail switching points are required at the intersections between radial and toroidal branches. A translational switching mechanism is proposed. The crane carriage consists of two independent sub-carriages, each composed of four wheels. A set of four secondary wheels attached to the main carriage prevents the crane tilting due to the CoG misalignment of some loads. The elevation system proposed consists of an electromechanical crane of four independent drums and 50 tonnes payload. In parallel with the crane design, a logistics and space availability study has been carried out, leading to the detection of clearance or transport problems that could be taken into account in the final crane design.

  14. ITER Remote Maintenance System (IRMS) lifecycle management

    Energy Technology Data Exchange (ETDEWEB)

    Tesini, Alessandro, E-mail: alessandro.tesini@iter.org [ITER Organization, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Otto' , Bede [Oxford Technologies Ltd, 7, Nuffield Way, Abingdon, Oxon OX14 1RJ (United Kingdom); Blight, John [FAAST 31c Allee de la Granette, 13600 Ceyreste (France); Choi, Chang-Hwan; Friconneau, Jean-Pierre; Gotewal, Krishan Kumar; Hamilton, David [ITER Organization, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Heckendorn, Frank [FD Technologies, PO Box 6686, Aiken, SC (United States); Martins, Jean-Pierre [ITER Organization, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Marty, Thomas [Westinghouse, 122, avenue de Hambourg, 13008 Marseille (France); Nakahira, Masataka; Palmer, Jim; Subramanian, Rajendran [ITER Organization, CS 90 046, 13067 St. Paul Lez Durance Cedex (France)

    2011-10-15

    The availability of the ITER machine to perform its scientific program is strongly dependent on the performance of the different Remote Handling (RH) systems constituting the ITER Remote Maintenance System (IRMS). The lifecycle of the IRMS will largely exceed 40 years from initial concept design and proof testing through to machine decommissioning. Such a long lifecycle requires that a rigorous approach is put in place to guarantee the technical capabilities of the highly innovative IRMS, its efficiency and its availability. For this purpose, an IRMS System Engineering and IRMS lifecycle management approach has been adopted by ITER. The approach aims at ensuring the IRMS full operability and availability at an acceptable cost of ownership over the full ITER machine assembly and operations period. The IRMS lifecycle management method described in this paper covers such subjects as specific requirements for IRMS design reviews, monitoring during manufacture, factory and site acceptance testing, integrated commissioning, decontamination, maintenance and re-qualification strategies, requirements for Integrated Logistical Support during operations. The updating and implementation of the IRMS lifecycle strategy and this procedure will be managed and monitored by the Remote Handling Integrated Product Team (RH-IPT). Although developed for the IRMS, the basic principles and procedures of lifecycle management could be applied to other ITER plant systems whose reliability and availability will be essential for the continued operation of the ITER machine.

  15. ITER Remote Maintenance System (IRMS) lifecycle management

    International Nuclear Information System (INIS)

    Tesini, Alessandro; Otto', Bede; Blight, John; Choi, Chang-Hwan; Friconneau, Jean-Pierre; Gotewal, Krishan Kumar; Hamilton, David; Heckendorn, Frank; Martins, Jean-Pierre; Marty, Thomas; Nakahira, Masataka; Palmer, Jim; Subramanian, Rajendran

    2011-01-01

    The availability of the ITER machine to perform its scientific program is strongly dependent on the performance of the different Remote Handling (RH) systems constituting the ITER Remote Maintenance System (IRMS). The lifecycle of the IRMS will largely exceed 40 years from initial concept design and proof testing through to machine decommissioning. Such a long lifecycle requires that a rigorous approach is put in place to guarantee the technical capabilities of the highly innovative IRMS, its efficiency and its availability. For this purpose, an IRMS System Engineering and IRMS lifecycle management approach has been adopted by ITER. The approach aims at ensuring the IRMS full operability and availability at an acceptable cost of ownership over the full ITER machine assembly and operations period. The IRMS lifecycle management method described in this paper covers such subjects as specific requirements for IRMS design reviews, monitoring during manufacture, factory and site acceptance testing, integrated commissioning, decontamination, maintenance and re-qualification strategies, requirements for Integrated Logistical Support during operations. The updating and implementation of the IRMS lifecycle strategy and this procedure will be managed and monitored by the Remote Handling Integrated Product Team (RH-IPT). Although developed for the IRMS, the basic principles and procedures of lifecycle management could be applied to other ITER plant systems whose reliability and availability will be essential for the continued operation of the ITER machine.

  16. ITER operating limit definition criteria

    International Nuclear Information System (INIS)

    Ciattaglia, S.; Barabaschi, P.; Carretero, J.A.; Chiocchio, S.; Hureau, D.; Girard, J.Ph.; Gordon, C.; Portone, A.; Rodrigo, L. Rodriguez; Roldan, C.; Saibene, G.; Uzan-Elbez, J.

    2009-01-01

    The operating limits and conditions (OLCs) are operating parameters and conditions, chosen among all system/components, which, together, define the domain of the safe operation of ITER in all foreseen ITER states (operation, maintenance, commissioning). At the same time they are selected to guarantee the required operation flexibility which is a critical factor for the success of an experimental machine such as ITER. System and components that are important for personnel or public safety (safety important class, SIC) are identified considering their functional importance in the overall plant safety analysis. SIC classification has to be presented already in the preliminary safety analysis report and approved by the licensing authority before manufacturing and construction. OLCs comprise the safety limits that, if exceeded, could result in a potential safety hazard, the relevant settings that determine the intervention of SIC systems, and the operational limits on equipment which warn against or stop a functional deviation from a planned operational status that could challenge equipment and functions. Some operational conditions, e.g. in-Vacuum Vessel (VV) radioactive inventories, will be controlled through procedures. Operating experience from present tokamaks, in particular JET, and from nuclear plants, is considered to the maximum possible extent. This paper presents the guidelines for the development of the ITER OLCs with particular reference to safety limits.

  17. ITER Operating Limits and Conditions

    International Nuclear Information System (INIS)

    Ciattaglia, S.; Barabaschi, P.; Carretero, J.A.

    2006-01-01

    The Operating Limits and Conditions (OLCs) are operating parameters and conditions, chosen among all system/components, which together define the domain of the safe operation of ITER in all foreseen ITER status (operation, maintenance, commissioning). At the same time they are selected to guarantee the required operation flexibility which is a critical factor for the success of an experimental machine such as ITER. System and components important for personnel or public safety (Safety Important Class, SIC) are identified from the overall plant safety analysis on functional importance to safety of the components. SIC classification has to be presented already inside the preliminary safety analysis report and approved by the licensing safety authority before the relevant construction. OLCs comprise the safety limits, i.e. that if exceeded could result in a potential safety hazard, the relevant settings that determine the intervention of SIC systems and the operational limits on equipment which warn from or stop a functional departure from a planned operational status that could challenge equipment and functions. The safety limits have to indicate clearly states that leave the nominal safety state of ITER; they are derived from the safety analysis of ITER. OLCs can represent in some cases few parameters grouping together. Some operational conditions, e.g. inventories, will be controlled through no real time measurements and procedures. Operating experience from present tokamaks, in particular JET, and from nuclear plants is considered at the maximum possible extent. This paper presents the guidelines to develop the ITER OLCs with particular reference to safety limits. A few examples are reported as well as open issues on some OLCs control and measurement and the relevant R-and-D planned to solve the issues. (author)

  18. ITER-FEAT operation

    International Nuclear Information System (INIS)

    Shimomura, Y.; Huguet, M.; Mizoguchi, T.; Murakami, Y.; Polevoi, A.R.; Shimada, M.; Aymar, R.; Chuyanov, V.A.; Matsumoto, H.

    2001-01-01

    ITER is planned to be the first fusion experimental reactor in the world operating for research in physics and engineering. The first ten years of operation will be devoted primarily to physics issues at low neutron fluence and the following ten years of operation to engineering testing at higher fluence. ITER can accommodate various plasma configurations and plasma operation modes, such as inductive high Q modes, long pulse hybrid modes and non-inductive steady state modes, with large ranges of plasma current, density, beta and fusion power, and with various heating and current drive methods. This flexibility will provide an advantage for coping with uncertainties in the physics database, in studying burning plasmas, in introducing advanced features and in optimizing the plasma performance for the different programme objectives. Remote sites will be able to participate in the ITER experiment. This concept will provide an advantage not only in operating ITER for 24 hours a day but also in involving the worldwide fusion community and in promoting scientific competition among the ITER Parties. (author)

  19. ITER-FEAT operation

    International Nuclear Information System (INIS)

    Shimomura, Y.; Huget, M.; Mizoguchi, T.; Murakami, Y.; Polevoi, A.; Shimada, M.; Aymar, R.; Chuyanov, V.; Matsumoto, H.

    2001-01-01

    ITER is planned to be the first fusion experimental reactor in the world operating for research in physics and engineering. The first 10 years' operation will be devoted primarily to physics issues at low neutron fluence and the following 10 years' operation to engineering testing at higher fluence. ITER can accommodate various plasma configurations and plasma operation modes such as inductive high Q modes, long pulse hybrid modes, non-inductive steady-state modes, with large ranges of plasma current, density, beta and fusion power, and with various heating and current drive methods. This flexibility will provide an advantage for coping with uncertainties in the physics database, in studying burning plasmas, in introducing advanced features and in optimizing the plasma performance for the different programme objectives. Remote sites will be able to participate in the ITER experiment. This concept will provide an advantage not only in operating ITER for 24 hours per day but also in involving the world-wide fusion communities and in promoting scientific competition among the Parties. (author)

  20. Alara applied to iter design and operation

    International Nuclear Information System (INIS)

    Uzan-Elbez, Joelle; Rodriguez-Rodrigo, Lina; Porfiri, Maria Teresa; Taylor, Neil; Gordon, Charles; Garin, Pascal; Girard, Jean-Philippe

    2005-01-01

    Based on the existing data on ITER and the safety options for licensing ITER in Cadarache, the present work assesses the application of the as-low-as-reasonably-achievable (ALARA) principle, as it has been implemented in the design of ITER and will be applied during ITER operation, as well as the compliance of the design with EUR/96-29 directive and regulation applicable in France. The preliminary occupational radiation exposure estimate gives a value of about 250 man mSv/a, which is half the annual target for ITER and comes essentially from maintenance activities. Some examples of the approach are presented

  1. The ITER Remote Maintenance Management System

    International Nuclear Information System (INIS)

    Tesini, Alessandro; Rolfe, A.C.

    2009-01-01

    A major challenge for the ITER project is to develop and implement a Remote Maintenance System, which can deliver high Tokamak availability within the constraints of the overall ITER programme objectives. Much of the maintenance of ITER will be performed using remote handling methods and some with combined manual and remote activities working together. The organization and management of the ITER remote handling facilities will be of a scale unlike any other remote handling application in the world. The ITER remote handling design and procurement activities will require co-ordination and management across many different sites throughout the world. It will be a major challenge for the ITER project to ensure a consistent quality and technical approach in all of the contributing parties. To address this issue the IO remote handling team are implementing the ITER Maintenance Management Plan (IMMP) comprising an overarching document defining the policies and methodologies (ITER Remote Maintenance Management System or IMMS) and an associated ITER remote handling code of practise (IRHCOP). The IMMS will be in document form available as a pdf file or similar. The IRHCOP will be implemented as a web based application and will provide access to the central resource of the entire code of practise from any location in the world. The IRHCOP data library will be centrally controlled in order that users can be assured of the data relevance and authenticity. This paper will describe the overall approach being taken to deal with this challenge and go on to detail the structure and content of both the IMMS and the IRHCOP.

  2. Guidelines for Remote Handling Maintenance of ITER Neutral Beam Components

    International Nuclear Information System (INIS)

    Cordier, J.-J.; Hemsworth, R.; Bayetti, P.

    2006-01-01

    Remote handling maintenance of ITER components is one of the main challenges of the ITER project. This type of maintenance shall be operational for the nuclear phase of exploitation of ITER, and be considered at a very early stage since it significantly impacts on the components design, interfaces management and integration business. A large part of the R/H equipment will be procured by the EU partner, in particular the whole Neutral Beam Remote Handling (RH) equipment package. A great deal of work has already been done in this field during the EDA phase of ITER project, but improvements and alternative option that are now proposed by ITER lead to added RH and maintenance engineering studies. The Neutral Beam Heating -and- Current Drive system 1 is being revisited by the ITER project. The vertical maintenance scheme that is presently considered by ITER, may significantly impact on the reference design of the Neutral Beam (NB) system and associated components and lead to new design of the NB box itself. In addition, revision of both NB cell radiation level zoning and remote handling classification of the beam line injector will also significantly impact on components design and maintenance. Based on the experience gained on the vertical maintenance scheme, developed in detail for the ITER Neutral Beam Test Facility 2 to be built in Europe in a near future, guidelines for the revision of the design and preliminary feasibility study of the remote handling vertical maintenance scheme of beam line components are described in the paper. A maintenance option for the SINGAP3 accelerator is also presented. (author)

  3. Maintenance schemes for the ITER neutral beam test facility

    International Nuclear Information System (INIS)

    Zaccaria, P.; Dal Bello, S.; Marcuzzi, D.; Masiello, A.; Coniglio, A.; Antoni, V.; Cordier, J.J.; Hemsworth, R.; Jones, T.; Di Pietro, E.; Mondino, P.L.

    2004-01-01

    The ITER neutral beam test facility (NBTF) is planned to be built, after the approval of the ITER construction and the choice of the ITER site, with the agreement of the ITER International Team and of the JA and RF participant teams. The key purpose is to progressively increase the performance of the first ITER injector and to demonstrate its reliability at the maximum operation parameters: power delivered to the plasma 16.5 MW, beam energy 1 MeV, accelerated D - ion current 40 A, pulse length 3600 s. Several interventions for possible modifications and for maintenance are expected during the early operation of the ITER injector in order to optimize the beam generation, aiming and steering. The maintenance scheme and the related design solutions are therefore a very important aspect to be considered for the NBTF design. The paper describes consistently the many interrelated aspects of the design, such as the optimisation of the vessel and cryopump geometry, in order to get a better maintenance flexibility, an easier man access and a larger access for diagnostic and monitoring. (authors)

  4. The ITER EC H and CD Upper Launcher: Maintenance concepts

    International Nuclear Information System (INIS)

    Ronden, D.M.S.; Baar, M. de; Chavan, R.; Elzendoorn, B.S.Q.; Grossetti, G.; Heemskerk, C.J.M.; Koning, J.F.; Landis, J.-D.; Spaeh, P.; Strauss, D.

    2013-01-01

    Highlights: ► We explain how an overall maintenance strategy defines individual maintenance tasks. ► Concepts are presented for replacement strategies of the in-vessel optical components. ► Vertical placement of the Upper Launcher in the Hot Cell may simplify maintenance. -- Abstract: Maintenance of the ITER EC H and CD Upper Launcher (UL) shall be performed through the use of Remote Handling (RH) in the ITER Hot Cell Facility (HCF). The UL design will have to be fully compliant with ITER RH maintenance requirements and the set of RH tooling and services available in the HCF. This paper describes the development of an overall maintenance strategy for the UL, starting from a listing of all conceivable maintenance operations, including hands-on tasks. Components for which design concepts are discussed in this paper are the Blanket Shield Module (BSM), the steering mirror (M4), the mid optics (M1, M2) and the waveguide (WG) feed-through plate. Aspects related to RH documentation, overall maintenance strategy and design concepts for optimizing the maintainability of the UL are presented

  5. Analysis of ITER upper port plug remote handling maintenance scenarios

    International Nuclear Information System (INIS)

    Koning, J.F.; Baar, M.R. de; Elzendoorn, B.S.Q.; Heemskerk, C.J.M.; Ronden, D.M.S.; Schuth, W.J.

    2012-01-01

    Highlights: ► Remote Handling Study Centre: providing RH compatibility analysis. ► Simulation: virtual reality including kinematics and realtime physics simulator. ► Applied on analysis of RH compatibility of Upper Launcher component replacement. ► Resulting in lowered maintenance procedure time and lessons learned. - Abstract: The ITER tokamak has a modular design, with port plugs, blanket modules and divertor cassettes. This set-up allows for maintenance of diagnostics, heating systems and first wall elements. The maintenance can be done in situ, or in the Hot Cell. Safe and effective remote handling (RH) will be ensured by the RH requirements and standards. Compliance is verified through remote handling compatibility assessments at the ITER Design Review milestones. The Remote Handling Study Centre at FOM Institute DIFFER is created to study ITER RH maintenance processes at different levels of complexity, from relatively simple situational awareness checks using snap-shots in the CAD system, time studies using virtual reality (VR) animations, to extensive operational sequence validation with multiple operators in real-time. The multi-operator facility mimics an RH work-cell as presently foreseen in the ITER RH control room. Novel VR technology is used to create a realistic setting in which a team of RH operators can interact with virtual ITER environments. A physics engine is used to emulate real-time contact interaction as to provide realistic haptic feed-back. Complex interactions between the RH operators and the control room system software are tested. RH task performance is quantified and operational resource usage estimated. The article provides a description and lessons learned from a recent study on replacement of the Steering Mirror Assembly on the ECRH (Electron Cyclotron Resonance Heating) Upper Launcher port plug.

  6. Analysis of ITER upper port plug remote handling maintenance scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Koning, J.F., E-mail: j.f.koning@heemskerk-innovative.nl [FOM Institute DIFFER - Dutch Institute for Fundamental Energy Research, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster and ITER-NL, PO Box 1207, 3430 BE Nieuwegein (Netherlands); Baar, M.R. de; Elzendoorn, B.S.Q. [FOM Institute DIFFER - Dutch Institute for Fundamental Energy Research, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster and ITER-NL, PO Box 1207, 3430 BE Nieuwegein (Netherlands); Heemskerk, C.J.M. [Heemskerk Innovative Technology, Noordwijk (Netherlands); Ronden, D.M.S.; Schuth, W.J. [FOM Institute DIFFER - Dutch Institute for Fundamental Energy Research, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster and ITER-NL, PO Box 1207, 3430 BE Nieuwegein (Netherlands)

    2012-08-15

    Highlights: Black-Right-Pointing-Pointer Remote Handling Study Centre: providing RH compatibility analysis. Black-Right-Pointing-Pointer Simulation: virtual reality including kinematics and realtime physics simulator. Black-Right-Pointing-Pointer Applied on analysis of RH compatibility of Upper Launcher component replacement. Black-Right-Pointing-Pointer Resulting in lowered maintenance procedure time and lessons learned. - Abstract: The ITER tokamak has a modular design, with port plugs, blanket modules and divertor cassettes. This set-up allows for maintenance of diagnostics, heating systems and first wall elements. The maintenance can be done in situ, or in the Hot Cell. Safe and effective remote handling (RH) will be ensured by the RH requirements and standards. Compliance is verified through remote handling compatibility assessments at the ITER Design Review milestones. The Remote Handling Study Centre at FOM Institute DIFFER is created to study ITER RH maintenance processes at different levels of complexity, from relatively simple situational awareness checks using snap-shots in the CAD system, time studies using virtual reality (VR) animations, to extensive operational sequence validation with multiple operators in real-time. The multi-operator facility mimics an RH work-cell as presently foreseen in the ITER RH control room. Novel VR technology is used to create a realistic setting in which a team of RH operators can interact with virtual ITER environments. A physics engine is used to emulate real-time contact interaction as to provide realistic haptic feed-back. Complex interactions between the RH operators and the control room system software are tested. RH task performance is quantified and operational resource usage estimated. The article provides a description and lessons learned from a recent study on replacement of the Steering Mirror Assembly on the ECRH (Electron Cyclotron Resonance Heating) Upper Launcher port plug.

  7. ITER safety and operational scenario

    International Nuclear Information System (INIS)

    Shimomura, Y.; Saji, G.

    1998-01-01

    The safety and environmental characteristics of ITER and its operational scenario are described. Fusion has built-in safety characteristics without depending on layers of safety protection systems. Safety considerations are integrated in the design by making use of the intrinsic safety characteristics of fusion adequate to the moderate hazard inventories. In addition to this, a systematic nuclear safety approach has been applied to the design of ITER. The safety assessment of the design shows how ITER will safely accommodate uncertainties, flexibility of plasma operations, and experimental components, which is fundamental in ITER, the first experimental fusion reactor. The operation of ITER will progress step by step from hydrogen plasma operation with low plasma current, low magnetic field, short pulse and low duty factor without fusion power to deuterium-tritium plasma operation with full plasma current, full magnetic field, long pulse and high duty factor with full fusion power. In each step, characteristics of plasma and optimization of plasma operation will be studied which will significantly reduce uncertainties and frequency/severity of plasma transient events in the next step. This approach enhances reliability of ITER operation. (orig.)

  8. Analysis of the ITER cryoplant operational modes

    International Nuclear Information System (INIS)

    Henry, D.; Journeaux, J.Y.; Roussel, P.; Michel, F.; Poncet, J.M.; Girard, A.; Kalinin, V.; Chesny, P.

    2007-01-01

    In the framework of an EFDA task, CEA is carrying out an analysis of the various ITER cryoplant operational modes. According to the project integration document, ITER is designed to be operated 365 days per year in order to optimize the available time of the Tokamak. It is anticipated that operation will be performed in long periods separated by maintenance periods (e.g. 10 days continuous operation and 1 week break) with annual or bi-annual major shutdown periods of a few months for maintenance, further installation and commissioning. For this operation schedule, auxiliary subsystems like the cryoplant and the cryodistribution have to cope with different heat loads which depend on the different ITER operating states. The cryoplant consists of four identical 4.5 K refrigerators and two 80 K helium loops coupled with two LN2 modules. All of these cryogenic subsystems have to operate in parallel to remove the heat loads from the magnet, 80 K shields, cryopumps and other small users. After a brief recall of the main particularities of a cryogenic system operating in a Tokamak environment, the first part of this study is dedicated to the assessment of the main ITER operation states. A new design of refrigeration loop for the HTS current leads, the updated layout of the cryodistribution system and revised strategy for operations of the cryopumps have been taken into consideration. The relevant normal operating scenarios of the cryoplant are checked for the typical ITER operating states like plasma operation state, short term stand by, short term maintenance, or test and conditioning state. The second part of the paper is dedicated to the abnormal operating modes coming from the magnets and from those generated by the cryoplant itself. The occurrence of a fast discharge or a quench of the magnets generates large heat loads disturbances and produces exceptional high mass flow rates which have to be managed by the cryoplant, while a failure of a cryogenic component induces

  9. Verifying elementary ITER maintenance actions with the MS2 benchmark product

    NARCIS (Netherlands)

    Heemskerk, C. J. M.; Elzendoorn, B. S. Q.; Magielsen, A. J.; Schropp, G. Y. R.

    2011-01-01

    A new facility has been taken in operation to investigate the influence of visual and haptic feedback on the performance of remotely executed ITER RH maintenance tasks. A reference set of representative ITER remote handling maintenance tasks was included the master slave manipulator system (MS2)

  10. The European contribution to the ITER Remote Maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Damiani, C., E-mail: carlo.damiani@f4e.europa.eu [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Annino, C.; Balagué, S.; Bates, P.; Ceccanti, F.; Di Mascio, T.; Dubus, G.; Esqué, S.; Gonzalez, C.; Lewczanin, M.; Locke, D.; Mont, L.; Olajos, K.; Ranz, R.; Shuff, R.; Puiu, A.; Van Hille, C.; Van Uffelen, M. [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Choi, C.H.; Friconneau, J.P. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); and others

    2014-10-15

    Highlights: •The article introduces the needs for remote maintenance in ITER. •It also discusses some of the issues related to the cultural transition from tokamaks as plasma physics to nuclear reactors. •It highlights the related cultural change and the implications on plant topology and maintenance. •Then, it presents those remote handling systems that will be procured by Europe. •The article emphasises the need of a major involvement of industries from now on. -- Abstract: For a first-of-a-kind nuclear fusion reactor like ITER, remote maintainability of neutron-activated components is one of the key aspects of plant design and operations, and a fundamental ingredient for the demonstration of long-term viability of fusion as energy source. The European Domestic Agency (EU DA, i.e. Fusion for Energy, F4E) is providing important support to the ITER Organisation (IO) in specifying the functional requirements of the Remote Handling (RH) Procurement Packages (i.e. the subsystems allocated to EU DA belonging to the overall ITER Remote Maintenance Systems IRMS), and in performing design and R and D activities – with the support of national laboratories and industries – in order to define a sound concept for these packages. Furthermore, domestic industries are being involved in the subsequent detailed design, validation, manufacturing and installation activities, in order to actually fulfil our procurement-in-kind obligations. After an introduction to ITER Remote Maintenance, this paper will present status and next stages for the RH systems allocated to EU DA, and will also illustrate complementary aspects related to cross cutting technologies like radiation tolerant components and RH control systems. Finally, the way all these efforts are coordinated will be presented together with the overall implementation scenario and key milestones.

  11. Operations and maintenance philosophy

    International Nuclear Information System (INIS)

    DUNCAN, G.P.

    1999-01-01

    This Operations and Maintenance (O and M) Philosophy document is intended to establish a future O and M vision, with an increased focus on minimizing worker exposure, ensuring uninterrupted retrieval operations, and minimizing operation life-cycle cost. It is intended that this document would incorporate O and M lessons learned into on-going and future project upgrades

  12. Remote maintenance challenges presented in the ITER engineering design

    International Nuclear Information System (INIS)

    Burgess, T.W.; Herndon, J.N.; Schrock, S.L.; Lousteau, D.C.

    1995-01-01

    Leading fusion energy research institutions are currently engaged in the Engineering Design Activity for the International Thermonuclear Experimental Reactor (ITER). A tokamak reactor design is evolving which emphasizes high system performance in a minimum overall reactor and building size. The resulting high component density dictates careful attention to ITER remote maintenance considerations in the development of the configuration. The complexity and scale of ITER remote maintenance tasks are well beyond the scope of today's experience and technology. This paper discusses the remote maintenance philosophy, describes the basic configuration as it relates to maintenance, and describes the basic procedures and equipment required. Key enabling technology research and development needs are also addressed

  13. Development of radiation hardness components for ITER remote maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Ito, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yagi, Toshiaki; Morita, Yousuke

    1998-04-01

    In the ITER, in-vessel remote handling is required to assemble and maintain in-vessel components in DT operations. Since in-vessel remote handling systems must operate under intense gamma ray radiation exceeding 30 kGy/h, their components must have sufficiently high radiation hardness to allow maintenance long enough in ITER in-vessel environments. Thus, extensive radiation tests and quality improvement, including optimization of material compositions, have been conducted through the ITER R and D program to develop radiation hardness components that meet radiation doses from 10 to 100 MGy at 10 kGy/h. This paper presents the latest on radiation hardness component development conducted by the Japan Home Team as a contribution to the ITER. The remote handling components tested are categorized for use in robotic or viewing systems, or as common components. Radiation tests have been conducted on commercially available products for screening, on modified products, and on new products to improve the radiation hardness. (author)

  14. Development of radiation hardness components for ITER remote maintenance

    International Nuclear Information System (INIS)

    Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Ito, Akira; Yagi, Toshiaki; Morita, Yousuke

    1998-01-01

    In the ITER, in-vessel remote handling is required to assemble and maintain in-vessel components in DT operations. Since in-vessel remote handling systems must operate under intense gamma ray radiation exceeding 30 kGy/h, their components must have sufficiently high radiation hardness to allow maintenance long enough in ITER in-vessel environments. Thus, extensive radiation tests and quality improvement, including optimization of material compositions, have been conducted through the ITER R and D program to develop radiation hardness components that meet radiation doses from 10 to 100 MGy at 10 kGy/h. This paper presents the latest on radiation hardness component development conducted by the Japan Home Team as a contribution to the ITER. The remote handling components tested are categorized for use in robotic or viewing systems, or as common components. Radiation tests have been conducted on commercially available products for screening, on modified products, and on new products to improve the radiation hardness. (author)

  15. Introducing artificial depth cues to improve task performance in ITER maintenance actions

    NARCIS (Netherlands)

    Heemskerk, C.J.M.; Eendebak, P.T.; Schropp, G.Y.R.; Hermes, H.V.; Elzendoorn, B.S.Q.; Magielsen, A.J.

    2013-01-01

    Maintenance operations on ITER tokamak components will be largely performed by remote handling. In previous work it was shown that representative maintenance tasks could be performed significantly faster with direct visual feedback than with camera feedback. In post-test interviews, operators

  16. Advanced scenarios for ITER operation

    Energy Technology Data Exchange (ETDEWEB)

    Sips, A.C.C. [Max-Planck-Institut fuer Plasmaphysik, Garching (Germany)

    2004-07-01

    In thermonuclear fusion research using magnetic confinement, the tokamak is the leading candidate for achieving conditions required for a reactor. An international experiment, ITER is proposed as the next essential and critical step on the path to demonstrating the scientific and technological feasibility of fusion energy. ITER is to produce and study plasmas dominated by self heating. This would give unique opportunities to explore, in reactor relevant conditions, the physics of {alpha}-particle heating, plasma turbulence and turbulent transport, stability limits to the plasma pressure and exhaust of power and particles. Important new results obtained in experiments, theory and modelling, enable an improved understanding of the physical processes occurring in tokamak plasmas and give enhanced confidence in ITER achieving its goals. In particular, progress has been made in research to raise the performance of tokamaks, aimed to extend the discharge pulse length towards steady-state operation (advanced scenarios). Standard tokamak discharges have a current density increasing monotonically towards the centre of the plasma. Advanced scenarios on the other hand use a modified current density profile. Different advanced scenarios range from (i) plasmas that sustain a central region with a flat current density profile (zero magnetic shear), capable of operating stationary at high plasma pressure, to (ii) discharges with an off axis maximum of the current density profile (reversed magnetic shear in the core), able to form internal transport barriers, to increase the confinement of the plasma. The physics of advanced tokamak discharges is described, together with an overview of recent results from different tokamak experiments. International collaboration between experiments aims to provide a better understanding, control and optimisation of these plasmas. The ability to explore advanced scenarios in ITER is very desirable, in order to verify the result obtained in

  17. Multi-purpose deployer for ITER in-vessel maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang-Hwan, E-mail: Chang-Hwan.CHOI@iter.org [ITER Organization, Route de Vinon-sur-Verdon, 13115 St Paul lez Durance (France); Tesini, Alessandro; Subramanian, Rajendran [ITER Organization, Route de Vinon-sur-Verdon, 13115 St Paul lez Durance (France); Rolfe, Alan; Mills, Simon; Scott, Robin; Froud, Tim; Haist, Bernhard; McCarron, Eddie [Oxford Technologies Ltd., 7 Nuffield Way, Abingdon, OXON (United Kingdom)

    2015-10-15

    Highlights: • ITER RH system called as the multi-purpose deployer (MPD) is introduced. • The MPD performs dust and tritium inventory control, in-service inspection. • The MPD performs leak localization, in-vessel diagnostics maintenance. • The MPD has nine degrees of freedom with a payload capacity up to 2 tons. - Abstract: The multi-purpose deployer (MPD) is a general purpose in-vessel remote handling (RH) system in the ITER RH system. The MPD provides the means for deployment and handling of in-vessel tools or components inside the vacuum vessel (VV) for dust and tritium inventory control, in-service inspection, leak localization, and in-vessel diagnostics. It also supports the operation of blanket first wall maintenance and neutral beam duct liner module maintenance operations. This paper describes the concept design of the MPD. The MPD is a cask based system, i.e. it stays in the hot cell building during the machine operation, and is deployed to the VV using the cask system for the in-vessel operations. The main part of the MPD is the articulated transporter which provides transportation and positioning of the in-vessel tools or components. The articulated transporter has nine degrees of freedom with a payload capacity up to 2 tons. The articulated transporter can cover the whole internal surface of the VV by switching between the four equatorial RH ports. Additionally it can use two non-RH equatorial ports to transfer large tools or components. A concept for in-cask tool exchange is developed which minimizes the cask transportation by allowing the MPD to stay in the VV during the tool exchange.

  18. Operational limits and disruptions in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Tsunematsu, T; Mizoguchi, T; Yoshino, R [Japan Atomic Energy Research Inst., Tokyo (Japan); Borrass, K; Engelmann, F; Pacher, G; Pacher, H [Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.). NET Design Team; Cohen, S; Post, D [Princeton Univ., NJ (USA). Plasma Physics Lab.; Hogan, J; Uckan, N A [Oak Ridge National Lab., TN (USA); Krasheninnikov, S; Mukhovatov, V; Parail, V

    1990-12-15

    Detailed knowledge of the operational limits for beta, q and the plasma density will be required for successful and flexible operation of ITER. In this paper, the present data base and guidelines on operational limits and disruptions in the ITER design are presented. 10 refs., 1 fig.

  19. Iterants, Fermions and Majorana Operators

    Science.gov (United States)

    Kauffman, Louis H.

    Beginning with an elementary, oscillatory discrete dynamical system associated with the square root of minus one, we study both the foundations of mathematics and physics. Position and momentum do not commute in our discrete physics. Their commutator is related to the diffusion constant for a Brownian process and to the Heisenberg commutator in quantum mechanics. We take John Wheeler's idea of It from Bit as an essential clue and we rework the structure of that bit to a logical particle that is its own anti-particle, a logical Marjorana particle. This is our key example of the amphibian nature of mathematics and the external world. We show how the dynamical system for the square root of minus one is essentially the dynamics of a distinction whose self-reference leads to both the fusion algebra and the operator algebra for the Majorana Fermion. In the course of this, we develop an iterant algebra that supports all of matrix algebra and we end the essay with a discussion of the Dirac equation based on these principles.

  20. Measurement and control system for ITER remote maintenance equipment

    Energy Technology Data Exchange (ETDEWEB)

    Oka, Kiyoshi; Kakudate, Satoshi; Takeda, Nobukazu; Takiguchi, Yuji; Akou, Kentaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-04-01

    ITER in-vessel components such as blankets and divertors are categorized as scheduled maintenance components because they are subjected to severe plasma heat and particle loads. Blanket maintenance requires remote handling equipment and tools able to handle Heavy payloads of about 4 tons within a 2 mm precision tolerance. Divertor maintenance requires remote replacement of 60 cassettes with a dead weight of about 25 tons each. In the ITER R and D program, full-scale remote handling equipment for blanket and divertor maintenance has been designed and assembled for demonstration tests. This paper reviews the measurement and control system developed for full-scale remote handling equipment, the Japan Home Team contribution. (author)

  1. Measurement and control system for ITER remote maintenance equipment

    International Nuclear Information System (INIS)

    Oka, Kiyoshi; Kakudate, Satoshi; Takeda, Nobukazu; Takiguchi, Yuji; Akou, Kentaro

    1998-01-01

    ITER in-vessel components such as blankets and divertors are categorized as scheduled maintenance components because they are subjected to severe plasma heat and particle loads. Blanket maintenance requires remote handling equipment and tools able to handle Heavy payloads of about 4 tons within a 2 mm precision tolerance. Divertor maintenance requires remote replacement of 60 cassettes with a dead weight of about 25 tons each. In the ITER R and D program, full-scale remote handling equipment for blanket and divertor maintenance has been designed and assembled for demonstration tests. This paper reviews the measurement and control system developed for full-scale remote handling equipment, the Japan Home Team contribution. (author)

  2. Analysis and validation center for ITER RH maintenance scenarios in a virtual environment

    NARCIS (Netherlands)

    Elzendoorn, B. S. Q.; M.R. de Baar,; Hamilton, D.; Heemskerk, C. J. M.; Koning, J. F.; Ronden, D. M. S.

    2012-01-01

    A facility for detailed simulation of maintenance processes in the ITER Hot Cell Facility (HCF) has been taken into operation. The facility mimics the Remote Handling (RH) work-cells as are presently foreseen. Novel virtual reality (VR) technology, extended with a physics engine is used to create a

  3. ITER parametric analysis and operational performance

    International Nuclear Information System (INIS)

    Perkins, L.J.; Spears, W.R.; Galambos, J.D.

    1991-01-01

    One of the key components of the ITER Conceptual Design Activities (CDA) is the determination of optimum design, investigation of operation in various modes, recommendation of baseline performance specifications, studies of sensitivity of ITER design to uncertainties in physics, investigation of operational flexibility, assessment of alternative designs, and determination of implications for extrapolation to prospective DEMO reactors. These terms of reference are reported in this document. Refs, figs and tabs

  4. Strategy to maximize maintenance operation

    OpenAIRE

    Espinoza, Michael

    2005-01-01

    This project presents a strategic analysis to maximize maintenance operations in Alcan Kitimat Works in British Columbia. The project studies the role of maintenance in improving its overall maintenance performance. It provides strategic alternatives and specific recommendations addressing Kitimat Works key strategic issues and problems. A comprehensive industry and competitive analysis identifies the industry structure and its competitive forces. In the mature aluminium industry, the bargain...

  5. Assistance tools for generic definition of ITER maintenance tasks and scenarios in advanced supervisory control systems

    International Nuclear Information System (INIS)

    Zieba, Stéphane; Russotto, François-Xavier; Da Silva Simoes, Max; Measson, Yvan

    2013-01-01

    Highlights: ► Improve supervisory control systems for ITER in-vessel and hot cell maintenance. ► Optimize remote handling operations effectiveness, reliability and safety. ► Provide a generic description of the maintenance tasks and scenarios. ► Development of context-based assistances for operators and supervisor. ► Improvement of operator's situation awareness. -- Abstract: This paper concerns the improvement of supervisory control systems in the context of remote handling for the maintenance tasks in ITER. This work aims at providing a single formalism and tools to define in a generic way the ITER maintenance tasks and scenarios for in-vessel and hot cell operations. A three-layered approach is proposed to model these tasks and scenarios. Physical actions are defined for the scene elements. From these physical actions, behaviours are defined to represent high-level functionalities. Finally, interaction modes define the way that behaviours are achieved in terms of human–machine interactions. Case study concerning the blanket maintenance procedure is discussed concerning the contributions of the descriptive model and the context-based assistances to the activities of supervisory control

  6. Research and development of remote maintenance equipment for ITER divertor maintenance

    International Nuclear Information System (INIS)

    Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka

    2005-02-01

    To facilitate easy remote maintainability, the ITER divertor is divided into 60 cassettes, which are transported in the toroidal and radial directions for replacement through maintenance ports located every 90 degrees using the divertor remote maintenance equipment such as in- and ex-vessel transporters. The cassette of 25 tons has to be transported and installed in the vacuum vessel with a positioning accuracy less than 2 mm in the limited space of the vacuum vessel and maintenance port under the intense gamma radiation field. Based on these requirements, the following design and tests were performed. (1) Link mechanism was studied to apply to the transportation of the heavy cassette in the restricted space. A compact mechanism with links for transportation of heavy cassette is designed through the optimization of the link angle taking account of space requirement and force efficiency. As a test result, the lifting capacity of 30 tons (larger than the cassette weight of 25 tons) using two link mechanisms has been demonstrated in the limited space. (2) Compact link mechanism was also studied to apply for locking of the cassette through the optimization of the link angle taking account of space requirement and force efficiency. As a test result, the final positioning accuracy of 0.03 mm for the 25 tons-cassette installation on the vacuum vessel from the initial positioning error of 5 mm has been demonstrated, so that the test result satisfies the requirement less than 2 mm using the link mechanisms in the limited space. (3) Sensor-based control using simple sensors such as optical fiber for divertor maintenance was tested using the full-scale mock-up divertor cassette and remote maintenance equipment. As a result, it is found that the positioning accuracy of 0.16 mm has been achieved by the optical fiber sensor and this value is sufficient for sensor-based control. In addition, the maintenance operation has been carried out through the human-machine interface

  7. The use of virtual prototyping and simulation in ITER maintenance device development

    International Nuclear Information System (INIS)

    Mattila, J.; Siuko, M.; Saarinen, H.; Maekinen, H.; Verho, S.; Vilenius, M.; Palmer, J.; Irving, M.

    2006-01-01

    The ITER divertor maintenance takes place approximately every second year. The maintenance occurs in very harsh and mechanically complicated environment. Due to the critical nature of the maintenance operations, the maintenance equipment design and the operation cycle will be verified in DTP2 test platform, in Tampere, Finland. TUT/IHA is working on the ITER divertor maintenance devices. Due to the complexity of the operation environment and tasks to be performed, 3d models and kinematic simulation have been valuable tool when developing the devices. Further, IHA has integrated to the models also dynamic properties of the device, so that it can be discussed as a virtual prototype. The virtual prototype can be used to verify the operation of the device, the operation cycle and also as a platform for developing the control software for the device. For device development, the virtual prototype is used to analyze the dynamic behavior, loading and flexibility of the device. The virtual prototype was also connected to real hardware to verify the operation of one joint. Then, the virtual model in computer was run and the output of the joints was given to a hydraulic cylinder representing disturbance load for an other hydraulic cylinder, which was operating under control software and aiming to move smoothly regardless of the disturbance load. By that way we were able to verify that the real system operates close enough with the simulation model. The virtual model is also used to shorten the time to get the DTP2 platform working. The CMM control software is done with virtual models as ready as possible. The CMM virtual model is connected to one-joint control hardware which allows developing the controller software one joint at time. In this paper, also other possibilities to use virtual prototypes in ITER divertor maintenance development are discussed. (author)

  8. Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO

    Energy Technology Data Exchange (ETDEWEB)

    Merrill, B.J., E-mail: Brad.Merrill@inl.gov [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID (United States); Wong, C.P.C. [General Atomics, San Diego, CA 92186-5608 (United States); Cadwallader, L.C. [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID (United States); Abdou, M.; Morley, N.B. [University of California Los Angeles, Los Angeles, CA 90095-1597 (United States)

    2014-10-15

    A leading power reactor breeding blanket candidate for a fusion demonstration power plant (DEMO) being pursued by the US Fusion Community is the Dual Coolant Lead Lithium (DCLL) concept. The safety hazards associated with the DCLL concept as a reactor blanket have been examined in several US design studies. These studies identify the largest radiological hazards as those associated with the dust generation by plasma erosion of plasma blanket module first walls, oxidation of blanket structures at high temperature in air or steam, inventories of tritium bred in or permeating through the ferritic steel structures of the blanket module and blanket support systems, and the {sup 210}Po and {sup 203}Hg produced in the PbLi breeder/coolant. What these studies lack is the scrutiny associated with a licensing review of the DCLL concept. An insight into this process was gained during the US participation in the ITER Test Blanket Module (TBM) Program. In this paper we discuss the lessons learned during this activity and make safety proposals for the design of a Fusion Nuclear Science Facility (FNSF) or a DEMO that employs a lead lithium breeding blanket.

  9. Maintenance implications of critical components in ITER CXRS upper port plug design

    International Nuclear Information System (INIS)

    Koning, Jarich; Jaspers, Roger; Doornink, Jan; Ouwehand, Bernard; Klinkhamer, Friso; Snijders, Bart; Sadakov, Sergey; Heemskerk, Cock

    2009-01-01

    Already in the early phase of a design for ITER, the maintenance aspects should be taken into account, since they might have serious implications. This paper presents the arguments in support of the case for the maintainability of the design, notably if this maintenance is to be performed by advanced remote methods. This structure is compliant to the evolving maintenance strategy of ITER. Initial results of a Failure Mode Effects and Criticality Analysis (FMECA) and a development risk analysis for the ITER upper port plug no. 3, housing the Charge Exchange Recombination Spectroscopy (CXRS) diagnostic, are employed for the definition of the maintenance strategy. The CXRS upper port plug is essentially an optical system which transfers visible light from the plasma into a fiber bundle. The most critical component in this path is the first mirror (M1) whose reflectivity degrades during operation due to deposition and/or erosion dominated effects. Amongst other measures to mitigate these effects, the strategy is to allow for a replacement of this mirror. Therefore it is mounted on a retractable central tube. The main purpose of this tube is to make frequent replacements possible without hindering operation. The maintenance method in terms of time, geometry and spare part policy has a large impact on cost of the system and time usage in the hot cell. Replacement of the tube under vacuum and magnetic field seems infeasible due to the operational risk involved. The preferred solution is to have a spare tube available which is replaced in parallel with other maintenance operations on the vessel, as to avoid any interference in the hot cell with the shutdown scheduling. This avoids having to refurbish a full port plug and also allows for a more frequent replacement of M1, as we can replace the mirror anytime the vacuum vessel is vented, estimated to be once a year.

  10. Qualification method for a 1 MGy-tolerant front-end chip designed in 65 nm CMOS for the read-out of remotely operated sensors and actuators during maintenance in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Verbeeck, Jens, E-mail: jens.verbeeck@esat.kuleuven.be [KU Leuven (KUL), Div. LRD-MAGyICS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); Cao, Ying [KU Leuven (KUL), Div. LRD-MAGyICS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); Van Uffelen, Marco; Casellas, Laura Mont; Damiani, Carlo; Morales, Emilio Ruiz; Santana, Roberto Ranz [Fusion for Energy (F4E), c/Josep, no. 2, Torres Diagonal Litoral, Ed. B3, 08019 Barcelona (Spain); Meek, Richard; Haist, Bernhard [Oxford Technologies Ltd. (OTL), 7 Nuffield Way, Abingdon OX14 1RL (United Kingdom); Hamilton, David [ITER Organisation (IO), Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul les Durance Cedex (France); Steyaert, Michiel [KU Leuven, ESAT-MICAS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); Leroux, Paul [KU Leuven, ESAT-MICAS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); KU Leuven, ESAT, Advanced Integrated Sensing Lab (AdvISe), Kleinhoefstraat 4, 2440 Geel (Belgium)

    2015-10-15

    This paper describes the radiation qualification procedure for a 1 MGy-tolerant Application Specific Integrated Circuit (ASIC) developed in 65 nm CMOS technology. The chip is intended for the read-out of electrical signals of sensors and actuators during maintenance in ITER. First the general working principle of the ASIC is shown. The developed IC allows to read-out, condition and digitize multiple low bandwidth (<10 kHz) sensors. In addition the IC is able to multiplex the digitized sensor signals. To comply with ITER-relevant constraints an adapted radiation qualification procedure has been proposed. The radiation-qualification procedure describes the test criteria and test conditions of the developed ASICs, which are also compared with COTS alternatives, to meet the stringent qualification procedures for electronics exposed to radiation in ITER.

  11. Design for maintenance during operation

    International Nuclear Information System (INIS)

    Barton, P.H.; Lyerly, H.D.

    1976-01-01

    Design of a nuclear power plant for safe, reliable and efficient operation involves much more than theory, regulations, regulatory guides, procedures, inspectors, and even quality assurance. It also involves a full knowledge and understanding of the activities which must be carried out to operate and maintain the plant. It must be remembered that a nuclear power plant is different from fossil designs and the designer must constantly keep in mind that access by people to every component is required for maintenance

  12. Analysis and validation center for ITER RH maintenance scenarios in a virtual environment

    International Nuclear Information System (INIS)

    Elzendoorn, B.S.Q.; Baar, M. de; Hamilton, D.; Heemskerk, C.J.M.; Koning, J.F.; Ronden, D.M.S.

    2012-01-01

    A facility for detailed simulation of maintenance processes in the ITER Hot Cell Facility (HCF) has been taken into operation. The facility mimics the Remote Handling (RH) work-cells as are presently foreseen. Novel virtual reality (VR) technology, extended with a physics engine is used to create a realistic setting in which a team of Remote Handling (RH) operators can interact with a virtual Hot Cell environment. The physics engine is used to emulate the Hot Cell behavior and to provide tactile feed-back of the (virtual) slave. Multi-operator maintenance scenarios can be developed and tested in virtual reality. Complex interactions between the RH operators and the HCF control system software will be tested. Task performance will be quantified and operational resource consumption will be estimated.

  13. Analysis and validation center for ITER RH maintenance scenarios in a virtual environment

    Energy Technology Data Exchange (ETDEWEB)

    Elzendoorn, B.S.Q., E-mail: B.S.Q.Elzendoorn@rijnhuizen.nl [FOM-Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster and ITER-NL, PO Box 1207, 3430 BE, Nieuwegein (Netherlands); Baar, M. de [FOM-Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster and ITER-NL, PO Box 1207, 3430 BE, Nieuwegein (Netherlands); Hamilton, D. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul-lez-Durance Cedex (France); Heemskerk, C.J.M. [Heemskerk Innovative Technology, Sassenheim (Netherlands); Koning, J.F.; Ronden, D.M.S. [FOM-Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster and ITER-NL, PO Box 1207, 3430 BE, Nieuwegein (Netherlands)

    2012-03-15

    A facility for detailed simulation of maintenance processes in the ITER Hot Cell Facility (HCF) has been taken into operation. The facility mimics the Remote Handling (RH) work-cells as are presently foreseen. Novel virtual reality (VR) technology, extended with a physics engine is used to create a realistic setting in which a team of Remote Handling (RH) operators can interact with a virtual Hot Cell environment. The physics engine is used to emulate the Hot Cell behavior and to provide tactile feed-back of the (virtual) slave. Multi-operator maintenance scenarios can be developed and tested in virtual reality. Complex interactions between the RH operators and the HCF control system software will be tested. Task performance will be quantified and operational resource consumption will be estimated.

  14. Guidelines for remote handling maintenance of ITER neutral beam line components: Proposal of an alternate supporting system

    International Nuclear Information System (INIS)

    Cordier, J.J.; Bayetti, P.; Hemsworth, R.; David, O.; Friconneau, J.P.

    2007-01-01

    Remote handling (R/H) maintenance of ITER components is one of the main challenges of the ITER project. This type of maintenance shall be operational for the assembly and nuclear phase of exploitation of ITER. It must be considered at a very early stage since it significantly impacts on the components design, interfaces management, assembly, maintenance and integration aspects. A large part of the R/H equipment will be procured by the EU Participating Team, including the whole Neutral Beam R/H Equipment. The Neutral Beam Heating and Current Drive system (NB and CD) design is being revisited by the ITER project. A vertical maintenance scheme is presently considered which may significantly impact on the reference design and associated components and lead to a new design of the NB and CD vacuum tank. In addition, NB line components remote handling solutions are being studied. The neutral beam test facility ITER to be built in Europe in the near future is also based on the vertical NB maintenance scheme of beam line components. New design guidelines compliant for both the ITER NB and CD system and the NB test facility proposed by the CEA association are described in the paper

  15. Operations and maintenance - Safety challenges

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Liv [Oljedirektoratet, Stavanger (Norway)

    1999-07-01

    With the unsteady oil prices and the possible consequences of the deregulation of the European energy markets one may expect further optimization of operating and maintenance costs. One may also expect extended use of various risk-based optimization techniques such as RCM (Reliability Centered Maintenance) and RBI (Risk Based Inspection). This presentation addresses the need for further research and development in this area. Maintenance work is necessary, but it can also create risk. The accident statistics show many examples of this. The Norwegian petroleum industry's ability to learn from previous incidents is questioned. Maintenance staff must be well trained and possess the necessary routines. Technical documentation must be updated. Uncertainties with respect to future oil and gas prices combined with the effect of the deregulation of the European energy markets will lead to even more focus on cost-effective operations and maintenance. The need for long-term research and development is stressed. Risk based techniques such as RCM and RBI are extensively used in the defence industry and the nuclear industry, but applying them to the petroleum industry requires improved risk models. Ageing effects such as corrosion, erosion, fatigue etc. can be expected, but the capability to predict, monitor and control them should be improved. At present, not even the most sophisticated risk analysis can model ageing effects. The importance of efficient use of information technology (IT) is stressed. Improving the product quality and safety often requires new technology and so research and development is important. Close cooperation with the industry is required.

  16. Verifying elementary ITER maintenance actions with the MS2 benchmark product

    International Nuclear Information System (INIS)

    Heemskerk, C.J.M.; Elzendoorn, B.S.Q.; Magielsen, A.J.; Schropp, G.Y.R.

    2011-01-01

    A new facility has been taken in operation to investigate the influence of visual and haptic feedback on the performance of remotely executed ITER RH maintenance tasks. A reference set of representative ITER remote handling maintenance tasks was included the master slave manipulator system (MS2) benchmark product. The benchmark product was used in task performance tests in a representative two-handed dexterous manipulation test bed at NRG. In the setup, the quality of visual feedback was varied by exchanging direct view with indirect view setups in which visual feedback is provided via video cameras. Interaction forces were measured via an integrated force sensor. The impact of feedback quality on the performance of maintenance tasks at the level of handling individual parts was measured and analysed. Remote execution of the maintenance actions took roughly 3-5 times more time than hands-on. Visual feedback was identified as the dominant factor, including aspects like (lack of) operator control over camera placement, pan, tilt and zoom, lack of 3D perception, image quality, and latency. Haptic feedback was found to be important, but only in specific contact transition and constrained motion tasks.

  17. A functional approach for managing ITER operations

    International Nuclear Information System (INIS)

    Houtte, Didier van; Sagot, François; Okayama, Katsumi; Blackler, Kenneth

    2012-01-01

    Highlights: ► A function-oriented approach for defining and organizing all the functions required to perform the mission has been developed. ► A Functional Breakdown Structure providing a complete hierarchy of functions on multiple levels is presented. ► The FBS is used for giving a good visibility of ITER project needs and requirements. ► Reliability (R) and Inherent Availability (A I ) of basic functions are calculated from data on the structures, systems and components (failure rate and time to repair) for obtaining the Availability objectives of the ITER project. - Abstract: ITER is currently the most ambitious project on nuclear fusion research. Its objective is to demonstrate the feasibility of fusion as an energy source for the future. The complexity of the systems required to meet this challenge present many opportunities for omissions or incorrect assumptions. System engineering allows the engineer to deal with such a complexity by developing a Functional Breakdown Structure (FBS). Unlike a Plant Breakdown Structure (PBS), the FBS is a function-oriented tree, not a product-oriented tree. It details operations or activities that have to be performed as needed functions of the architecture, allowing identification of any missing elements, defining the personnel skills required to operate the architecture and managing the machine availability.

  18. ITER L 6 equatorial maintenance duct remote handling study

    International Nuclear Information System (INIS)

    Millard, J.

    1996-09-01

    The status and conclusions of a preliminary study of equatorial maintenance duct remote handling is reported. Due to issues with the original duct design a significant portion of the study had to be refocused on equatorial duct layout studies. The study gives an overview of some of the options for design of these ducts and the impact of the design on the equipment to work in the duct. To develop a remote handling concept for creating access through the ducts the following design tasks should be performed: define the operations sequences for equatorial maintenance duct opening and closing; review the remote handling requirements for equatorial maintenance duct opening and closing; design concept for door and pipe handling equipment and to propose preliminary procedures for material handling outsides the duct. 35 figs

  19. Construction of a test platform for Test Blanket Module (TBM) systems integration and maintenance in ITER Port Cell #16

    Energy Technology Data Exchange (ETDEWEB)

    Vála, Ladislav, E-mail: ladislav.vala@cvrez.cz [Centrum výzkumu Řež, Hlavní 130, 250 68 Husinec-Řež (Czech Republic); Reungoat, Mathieu, E-mail: mathieu.reungoat@cvrez.cz [Centrum výzkumu Řež, Hlavní 130, 250 68 Husinec-Řež (Czech Republic); Vician, Martin [Centrum výzkumu Řež, Hlavní 130, 250 68 Husinec-Řež (Czech Republic); Poitevin, Yves; Ricapito, Italo; Zmitko, Milan; Panayotov, Dobromir [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)

    2015-10-15

    Highlights: • A non-nuclear, full size facility – TBM platform – is under construction in CVR. • It is designed for tests, optimization and validation of TBS maintenance operations. • It will allow testing and validation of specific maintenance tools and RH equipment. • It reproduces ITER Port Cell #16, as well as the TBS interfaces and main equipment. • The TBM platform will be available for full operation in the first half of 2016. - Abstract: This paper describes a project of a non-nuclear, 1:1 scale testing platform dedicated to tests, optimization and validation of integration and maintenance operations for the European TBM systems in the ITER Port Cell #16. This TBM platform is currently under construction in Centrum výzkumu Řež, Czech Republic. The facility is realized within the scope of the SUSEN project and its full operation is foreseen in the first half of 2016.

  20. Conceptual design of cesium removal device for ITER NBI maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Oka, Kiyoshi; Shibanuma, Kiyoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    Cesium is required in order to generate a stable negative ion of hydrogen in an ion source of the neutral beam injector (NBI), which is one of the plasma-heating devices for International Thermonuclear Experimental Reactor (ITER). After long time operation of the NBI, the cesium deposits to the insulators supporting the electrode. Due to the deterioration of the insulation resistance, the continuous operation of the NBI will be difficult. In addition, the NBI device is activated by neutrons from D-T plasma, so that periodic removal and cleaning of the cesium on the insulators by remove handling is required. A study of the cesium removal scenario and the device is therefore required considering remote handling. In this report, a cesium removal procedure and conceptual design of the cesium removal device using laser ablation technique are studied, and the feasibility of the laser ablation method is shown. (author)

  1. Prevalence of operator fatigue in winter maintenance operations.

    Science.gov (United States)

    Camden, Matthew C; Medina-Flintsch, Alejandra; Hickman, Jeffrey S; Bryce, James; Flintsch, Gerardo; Hanowski, Richard J

    2018-02-02

    Similar to commercial motor vehicle drivers, winter maintenance operators are likely to be at an increased risk of becoming fatigued while driving due to long, inconsistent shifts, environmental stressors, and limited opportunities for sleep. Despite this risk, there is little research concerning the prevalence of winter maintenance operator fatigue during winter emergencies. The purpose of this research was to investigate the prevalence, sources, and countermeasures of fatigue in winter maintenance operations. Questionnaires from 1043 winter maintenance operators and 453 managers were received from 29 Clear Road member states. Results confirmed that fatigue was prevalent in winter maintenance operations. Over 70% of the operators and managers believed that fatigue has a moderate to significant impact on winter maintenance operations. Approximately 75% of winter maintenance operators reported to at least sometimes drive while fatigued, and 96% of managers believed their winter maintenance operators drove while fatigued at least some of the time. Furthermore, winter maintenance operators and managers identified fatigue countermeasures and sources of fatigue related to winter maintenance equipment. However, the countermeasures believed to be the most effective at reducing fatigue during winter emergencies (i.e., naps) were underutilized. For example, winter maintenance operators reported to never use naps to eliminate fatigue. These results indicated winter maintenance operations are impacted by operator fatigue. These results support the increased need for research and effective countermeasures targeting winter maintenance operator fatigue. Copyright © 2018 Elsevier Ltd. All rights reserved.

  2. Operation and control of ITER plasmas

    International Nuclear Information System (INIS)

    2001-01-01

    Features incorporated in the design of the International Thermonuclear Experimental Reactor (ITER) tokamak and its ancillary and plasma diagnostic systems that will facilitate operation and control of ignited and/or high-Q DT plasmas are presented. Control methods based upon straight-forward extrapolation of techniques employed in the present generation of tokamaks are found to be adequate and effective for DT plasma control with burn durations of ≥1000 s. Examples of simulations of key plasma control functions including magnetic configuration control and fusion burn (power) control are given. The prospects for the creation and control of steady-state plasmas sustained by non-inductive current drive are also discussed. (author)

  3. Operation and control of ITER plasmas

    International Nuclear Information System (INIS)

    1999-01-01

    Features incorporated in the design of the International Thermonuclear Experimental Reactor (ITER) tokamak and its ancillary and plasma diagnostic systems that will facilitate operation and control of ignited and/or high-Q DT plasmas are presented. Control methods based upon straight-forward extrapolation of techniques employed in the present generation of tokamaks are found to be adequate and effective for DT plasma control with burn durations of ≥1000 s. Examples of simulations of key plasma control functions including magnetic configuration control and fusion burn (power) control are given. The prospects for the creation and control of steady-state plasmas sustained by non-inductive current drive are also discussed. (author)

  4. Void Fraction Instrument operation and maintenance manual

    International Nuclear Information System (INIS)

    Borgonovi, G.; Stokes, T.I.; Pearce, K.L.; Martin, J.D.; Gimera, M.; Graves, D.B.

    1994-09-01

    This Operations and Maintenance Manual (O ampersand MM) addresses riser installation, equipment and personnel hazards, operating instructions, calibration, maintenance, removal, and other pertinent information necessary to safely operate and store the Void Fraction Instrument. Final decontamination and decommissioning of the Void Fraction Instrument are not covered in this document

  5. Operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Ackermann, G.

    1987-01-01

    This textbook gives a systematic introduction into the operational and maintenance activities in nuclear power plants with pressurized water reactors. Subjects: (1) Setup and operational behaviour of power reactors, (2) setup of nuclear power plants, (3) radiation protection and nuclear safety, (4) nuclear fuel, (5) constructional layout of nuclear power plants, (6) management, and (7) maintenance. 158 figs., 56 tabs

  6. Remote maintenance of a combined regeneration-isolation valve for the ITER Torus vacuum pumping system

    International Nuclear Information System (INIS)

    Stringer, J.; Blevins, J.

    1992-01-01

    A large diameter valve suitable for high vacuum operation is under study for ITER Torus evacuation. The valves must comply with specifications for leak-tightness, radiation resistance, dust tolerance, overpressure, and thermal gradients. Remote maintenance of the seal and valve moving parts without disturbance to the rest of the valve system is a requirement. This paper describes tow methods of seal exchange by remote means. In the first method, a flask is proposed for the valve moving parts exchange in inert gas, when the machine is shut down. In the second method a novel concept is described for seal exchange while under vacuum, without having to bring the machine up to atmosphere. The advantages of this method are that scheduled remote handling (RH) operations and outages for seal replacement are not required. Also, the need for a flask is avoided

  7. Development of a Remote Handling Robot for the Maintenance of an ITER-Like D-Shaped Vessel

    Directory of Open Access Journals (Sweden)

    Peihua Chen

    2014-01-01

    Full Text Available Robotic operation is one of the major challenges in the remote maintenance of ITER vacuum vessel (VV and future fusion reactors as inner operations of Tokamak have to be done by robots due to the internal adverse conditions. This paper introduces a novel remote handling robot (RHR for the maintenance of ITER-like D-shaped vessel. The modular designed RHR, which is an important part of the remote handling system for ITER, consists of three parts: an omnidirectional transfer vehicle (OTV, a planar articulated arm (PAA, and an articulated teleoperated manipulator (ATM. The task of RHR is to carry processing tools, such as the viewing system, leakage detector, and electric screwdriver, to inspect and maintain the components installed inside the D-shaped vessel. The kinematics of the OTV, as well as the kinematic analyses of the PAA and ATM, is studied in this paper. Because of its special length and heavy payload, the dynamics of the PAA is also investigated through a dynamic simulation system based on robot technology middleware (RTM. The results of the path planning, workspace simulations, and dynamic simulation indicate that the RHR has good mobility together with satisfying kinematic and dynamic performances and can well accomplish its maintenance tasks in the ITER-like D-shaped vessel.

  8. Maintenance implications of critical components in ITER CXRS upper port plug design

    NARCIS (Netherlands)

    Koning, J.; Jaspers, R.; Doornink, J.; Ouwehand, B.; Klinkhamer, J.F.F.; Snijders, B.; Sadakov, S.; Heemskerk, C.

    2009-01-01

    Already in the early phase of a design for ITER, the maintenance aspects should be taken into account, since they might have serious implications. This paper presents the arguments in support of the case for the maintainability of the design, notably if this maintenance is to be performed by

  9. Analysis of the ITER ECH Upper Port Launcher remote maintenance using virtual reality

    NARCIS (Netherlands)

    Elzendoorn, B.; Baar, M. de; Chavan, R.; Goodman, T.; Heemskerk, C.; Heidinger, R.; Kleefeldt, K.; Koning, J.; Sanders, S.; Späh, P.; Strauss, D.; Verhoeven, T.; Vreede, F. de

    2009-01-01

    All ITER sub-systems of remote handling (RH) classes 1 and 2 have to be remotely maintainable. The maintenance strategy for these components has to ensure system availability after failure or scheduled maintenance. This paper shows how virtual reality (VR) simulation [1] can be used as a tool to

  10. Introducing artificial depth cues to improve task performance in ITER maintenance actions

    International Nuclear Information System (INIS)

    Heemskerk, C.J.M.; Eendebak, P.T.; Schropp, G.Y.R.; Hermes, H.V.; Elzendoorn, B.S.Q.; Magielsen, A.J.

    2013-01-01

    Highlights: ► Operators regard lack of 3D perception as primary factor hindering remote maintenance. ► Promising techniques to improve depth perception are depth gauges and stereo vision. ► First experiment shows artificial depth gauges need to be designed with care. ► Second experiment shows that stereo vision improves task performance significantly. -- Abstract: Maintenance operations on ITER tokamak components will be largely performed by remote handling. In previous work it was shown that representative maintenance tasks could be performed significantly faster with direct visual feedback than with camera feedback. In post-test interviews, operators indicated that they regarded the lack of 3D perception as the primary factor hindering their performance. This paper discusses various techniques to improve depth perception in teleoperation, including stereo vision, head tracking, virtual camera views and depth gauges. The most promising techniques were tested. Performance metrics included time-to-complete, path analysis and operator work-load. In a first experiment, artificial depth gauges views were tested in a 1:1 scale hardware testbed with mechanical master-slave manipulators handled by experienced operators. Robust real-time image processing was achieved with marker-based objects. The simple depth gauge and graphical overlay did not significantly improve task performance. Operators commented on their view of the task being “obstructed” by the graphical overlay, and the depth gauge was judged not very informative. In a second experiment, real time tracking was combined with VR display including stereo and head tracking. While stereo was found to improve the task performance significantly over the 1 camera (mono) condition, head tracking unexpectedly did not

  11. Introducing artificial depth cues to improve task performance in ITER maintenance actions

    Energy Technology Data Exchange (ETDEWEB)

    Heemskerk, C.J.M., E-mail: c.heemskerk@heemskerk-innovative.nl [Heemskerk Innovative Technology, Sassenheim (Netherlands); Eendebak, P.T. [TNO Netherlands Organisation for Applied Scientific Research (Netherlands); Schropp, G.Y.R. [Heemskerk Innovative Technology, Sassenheim (Netherlands); Hermes, H.V. [TU Eindhoven (Netherlands); Elzendoorn, B.S.Q. [FOM Institute DIFFER (Dutch Institute for Fundamental Energy Research), Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, P.O. Box 1207, 3430 BE Nieuwegein (Netherlands); Magielsen, A.J. [NRG, P.O. Box 25, 1755 ZG Petten (Netherlands)

    2013-10-15

    Highlights: ► Operators regard lack of 3D perception as primary factor hindering remote maintenance. ► Promising techniques to improve depth perception are depth gauges and stereo vision. ► First experiment shows artificial depth gauges need to be designed with care. ► Second experiment shows that stereo vision improves task performance significantly. -- Abstract: Maintenance operations on ITER tokamak components will be largely performed by remote handling. In previous work it was shown that representative maintenance tasks could be performed significantly faster with direct visual feedback than with camera feedback. In post-test interviews, operators indicated that they regarded the lack of 3D perception as the primary factor hindering their performance. This paper discusses various techniques to improve depth perception in teleoperation, including stereo vision, head tracking, virtual camera views and depth gauges. The most promising techniques were tested. Performance metrics included time-to-complete, path analysis and operator work-load. In a first experiment, artificial depth gauges views were tested in a 1:1 scale hardware testbed with mechanical master-slave manipulators handled by experienced operators. Robust real-time image processing was achieved with marker-based objects. The simple depth gauge and graphical overlay did not significantly improve task performance. Operators commented on their view of the task being “obstructed” by the graphical overlay, and the depth gauge was judged not very informative. In a second experiment, real time tracking was combined with VR display including stereo and head tracking. While stereo was found to improve the task performance significantly over the 1 camera (mono) condition, head tracking unexpectedly did not.

  12. The operation and maintenance manual

    International Nuclear Information System (INIS)

    Klein, W.; Krotil, H.; Stoll, A.

    1975-01-01

    The Operating Manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the Operating Manual. It contains, appropriately arranged, the necessary system and other diagrams, drawings, lists, licensing documents and similar material, which are necessary for understanding the design, for testing, for obtaining the operating licence and for the operation of individual systems and of the entire plant. (orig./RW) [de

  13. The operation and maintenance manual

    International Nuclear Information System (INIS)

    Stoll, A.; Krotil, H.; Klein, W.

    1976-01-01

    The operating manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the operating manual. The operating manual is an essential element in bringing man and machine in harmony. This is necessary for safe and, as far as possible, uninterrupted operation of the power plant. The operating manual is the only document containing binding instructions for plant operation. All the tasks of plant operation which are carried out by plant staff are described in the operating manual in a form which is as clear and comprehensible as possible. A considerable number of these tasks can only be carried out by man, namely: 1) tasks concerning operational organization, 2) all non-automated areas of plant operation. (orig./TK) [de

  14. Simulation and Analysis of the Hybrid Operating Mode in ITER

    International Nuclear Information System (INIS)

    Kessel, C.E.; Budny, R.V.; Indireshkumar, K.

    2005-01-01

    The hybrid operating mode in ITER is examined with 0D systems analysis, 1.5D discharge scenario simulations using TSC and TRANSP, and the ideal MHD stability is discussed. The hybrid mode has the potential to provide very long pulses and significant neutron fluence if the physics regime can be produced in ITER. This paper reports progress in establishing the physics basis and engineering limitation for the hybrid mode in ITER

  15. New achievements of the Divertor Test Platform programme for the ITER divertor remote maintenance R and D

    International Nuclear Information System (INIS)

    Damiani, C.; Baldi, L.; Galbiati, L.; Irving, M.; Lorenzelli, L.; Micciche, G.; Muro, L.; Nucci, S.; Varocchi, G.; Poggianti, A.; Fermani, G.; Maisonnier, D.; Palmer, J.; Martin, E.; Friconneau, J.P.; Gravez, P.; Takeda, N.

    2001-01-01

    The divertor assembly for the ITER fusion reactor consists of a number of rail mounted cassettes (54 now in ITER FEAT) located in the bottom region of the vacuum vessel. These cassettes shall be removed/installed remotely during the life of the reactor by means of specific devices. To demonstrate and optimise the feasibility of the in-vessel maintenance process the Divertor Test Platform (DTP) has been established at the ENEA Research Centre in Brasimone, Italy, as a major part of the large ITER R and D project L7. A first set of tests has been already carried out and reported during 1998, when the basic feasibility of the divertor replacement was demonstrated. In the present period (January 1999-July 2000), new activities, including both site tests and other 'external' R and D works, have been carried out in order to refine and improve the ITER divertor maintenance scenario. These include the study of abnormal maintenance operations and of possible handling equipment failure and its consequences; the procurement and testing of new sub-systems (e.g. a force reflection manipulator arm), and the development of remote handling techniques including a virtual reality system. Following a short description of the DTP, this paper reports on the new results and achievements, draws the relevant conclusions, and finally discusses future activities

  16. Maintenance analysis method and operational feedback: a comprehensive maintenance management

    International Nuclear Information System (INIS)

    Mathieu Riou; Victor Planchon

    2006-01-01

    Full text of publication follows: Current periodic inspections program carried out on the COGEMA LOGISTICS casks is required by regulations and approved by the competent Authority. Thus, Safety and casks conformity to the according certificate of approval are guaranteed. Nonetheless, based on experience it appeared that some maintenance operations did not seem relevant or were redundant. Then, it was decided to rethink completely our maintenance program to reach the following objectives: - Set up the 'a minima' required inspection operations required to guarantee Safety and conformity to the certificate of approval, - Optimize criteria and periodicities of inspections taking into account: operational feedback, routine inspections carried out for each transport, regulations, environmental impact (ALARA, waste reduction,...), cost-effectiveness (reduction of cask's immobilization period,...). - Set up a maintenance program in Safety Analysis Reports that: stands alone (no need to check the specification or the certificate of approval to have the complete list of inspections mandatory to guarantee Safety), gives objectives instead of means of controls. This approach needs then to be re-evaluated by the competent Authority. Study's scope has been limited to the TN TM 12 cask family which is intensely used. COGEMA LOGISTICS has a high operational feedback on these casks. After Authority agreement, and in accordance with its requirements, study will then be extended to the other casks belonging to the COGEMA LOGISTICS cask fleet. Actually, the term 'maintenance' is linked to 'Base maintenance' and 'Main maintenance' and implicitly means that the cask is immobilized for a given period. To emphasize the modifications, the term 'maintenance' is no longer used and is substituted by 'periodic upkeep'. By changing the name, COGEMA LOGISTICS wants to emphasize that: some operations can for instance be realized while the cask is unloaded, periodicities are thought in terms of

  17. Principles of machine operation and maintenance

    CERN Document Server

    Jeffrey, Dick

    2013-01-01

    This book explains how rotating machinery works, and the role of the maintenance engineer in ensuring its proper operation. Stress is laid on the need for the trainee engineer to develop skills in diagnosis and troubleshooting as well as practicalexpertise in maintenance procedures.

  18. Operations and maintenance plans for the TFTR

    International Nuclear Information System (INIS)

    Allen, H.L.; Fedor, B.J.

    1978-01-01

    Princeton University Plasma Physics Laboratory (PPPL) is constructing a Tokamak Fusion Test Reactor (TFTR) scheduled to begin operation for fusion research experiments in late 1981, first with hydrogen and deuterium plasmas and later, in the second phase, using tritium for high power fusion studies. This latter mode will introduce considerable complexity to operation and maintenance of the TFTR in terms of meeting requirements for tritium handling, adequate radiation shielding, and corrective and preventive maintenance procedures. In this paper we discuss plans for the installation and preoperational testing of the major subsystems of TFTR, proposed start-up and operating scenarios for the device and the system of operational control. In addition, the TFTR Maintenance Plan and related procedures for specific major maintenance tasks are described, including the use of remote handling equipment and remote manipulators. Each of these topics is addressed in terms of the current status of planning and development

  19. Singular point analysis during rail deployment into vacuum vessel for ITER blanket maintenance

    International Nuclear Information System (INIS)

    Kakudate, Satoshi; Shibanuma, Kiyoshi

    2007-05-01

    Remote maintenance of the ITER blanket composed of about 400 modules in the vessel is required by a maintenance robot due to high gamma radiation of ∼500Gy/h in the vessel. A concept of rail-mounted vehicle manipulator system has been developed to apply to the maintenance of the ITER blanket. The most critical issue of the vehicle manipulator system is the feasibility of the deployment of the articulated rail composed of eight rail links into the donut-shaped vessel without any driving mechanism in the rail. To solve this issue, a new driving mechanism and procedure for the rail deployment has been proposed, taking account of a repeated operation of the multi-rail links deployed in the same kinematical manner. The new driving mechanism, which is deferent from those of a usual 'articulated arm' equipped with actuator in the every joint for movement, is composed of three mechanisms. To assess the feasibility of the kinematics of the articulated rail for rail deployment, a kinematical model composed of three rail links related to a cycle of the repeated operation for rail deployment was considered. The determinant det J' of the Jacobian matrix J' was solved so as to estimate the existence of a singular point of the transformation during rail deployment. As a result, it is found that there is a singular point due to det J'=0. To avoid the singular point of the rail links, a new location of the second driving mechanism and the related rail deployment procedure are proposed. As a result of the rail deployment test based on the new proposal using a full-scale vehicle manipulator system, the respective rail links have been successfully deployed within 6 h less than the target of 8 h in the same manner of the repeated operation under a synchronized cooperation among the three driving mechanisms. It is therefore concluded that the feasibility of the rail deployment of the articulated rail composed of simple structures without any driving mechanism has been demonstrated

  20. Remote operational trials with the ITER FDR divertor handling equipment

    International Nuclear Information System (INIS)

    Irving, M.; Baldi, L.; Benamati, G.; Galbiati, L.; Giacomelli, S.; Lorenzelli, L.; Micciche, G.; Muro, L.; Polverari, A.; Palmer, J.; Martin, E.

    2003-01-01

    The ITER divertor test platform (DTP) located at ENEA's Research Centre in Brasimone, Italy is a full-scale mock-up of a 72 deg. arc of the ITER 1998 vessel divertor region--the result of a major initiative over the period 1996-2000. Since the implementation of this facility, the design of the ITER vessel--and therefore much of the remote maintenance equipment--has changed substantially. However, the nature and principles of the remote handling equipment are still very similar, and hence many valuable lessons can yet be learned from the existing equipment for the future. In particular, true remote handling tests of the major maintenance subsystems were seen as an important step in determining their suitability for ITER. This paper describes and documents a series of three, discrete, remote-handling trials carried out using most of the major DTP subsystems, and presents an overview of the conclusions and suggestions for future development of ITER cassette remote handling equipment

  1. RA reactor operation and maintenance

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-02-01

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air

  2. Analysis of the ITER ECH Upper Port Launcher remote maintenance using virtual reality

    International Nuclear Information System (INIS)

    Elzendoorn, Ben; de Baar, Marco; Chavan, Rene; Goodman, Timothy; Heemskerk, Cock; Heidinger, Roland; Kleefeldt, Klaus; Koning, Jarich; Sanders, Stephen; Spaeh, Peter; Strauss, Dirk; Verhoeven, Toon; Vreede, Fred de

    2009-01-01

    All ITER sub-systems of remote handling (RH) classes 1 and 2 have to be remotely maintainable. The maintenance strategy for these components has to ensure system availability after failure or scheduled maintenance. This paper shows how virtual reality (VR) simulation can be used as a tool to analyze the maintenance process, to predict the mean time to repair and to ensure the RH compatibility of one ITER sub-system, the Upper Port Launcher (UPL) . Special emphasis is put on the development of RH procedures and the identification of tooling requirements. The possibility to simulate RH logistics and repair actions in an early stage of the design process allows for the identification of those maintenance actions that require dedicated tests in the Launcher Handling Test Facility at Karlsruhe. The VR analysis, together with dedicated mock-up tests will demonstrate the RH compatibility of the UPL plug, provide input to the design of the Port Plug maintenance area in the ITER Hot Cell, and support the development of RH maintenance tooling.

  3. Communication links for fusion reactor maintenance operations

    International Nuclear Information System (INIS)

    Van Uffelen, M.

    2005-01-01

    Different architectures are envisaged for data transmission with fibre optic links in a radiation environment, as proposed in literature for both space and high energy physics applications. Their needs and constraints differ from those encountered for maintenance tasks in the future ITER environment, not only in terms of temperature and radiation levels, but also with respect to transmission speed requirements. Our approach attempts to limit the use of radiation-sensitive electronics for transmission of both digital and/or analogue data to the control room, using glass fibres as transport medium. We therefore assessed the radiation behaviour of a cost-effective fibre optic transmitter at 850 nm, consisting of a PWM (pulse width modulator), a radiation tolerant current driver (previously developed at SCK-CEN) and a VCSEL (Vertical-Cavity Surface Emitting Laser assembly, up to 10 MGy at 60 degrees Celsius. The PWM enables to transform an analogue sensor signal into a pseudo numerical signal, with a pulse width proportional to the incoming signal. The main objective of this task is to contribute to the major design of the maintenance equipment and strategy needed for the remote replacement of the divertor system in the future ITER fusion reactor, with particular attention to the implications of radiation hardening rules and recommendations. Next to the radiation assessment studies of remote handling tools, including actuators and sensors, we also develop radiation tolerant communication links with multiplexing capabilities

  4. ATLAS Maintenance and Operation management system

    CERN Document Server

    Copy, B

    2007-01-01

    The maintenance and operation of the ATLAS detector will involve thousands of contributors from 170 physics institutes. Planning and coordinating the action of ATLAS members, ensuring their expertise is properly leveraged and that no parts of the detector are understaffed or overstaffed will be a challenging task. The ATLAS Maintenance and Operation application (referred to as Operation Task Planner inside the ATLAS experiment) offers a fluent web based interface that combines the flexibility and comfort of a desktop application, intuitive data visualization and navigation techniques, with a lightweight service oriented architecture. We will review the application, its usage within the ATLAS experiment, its underlying design and implementation.

  5. Operation and maintenance of offshore wind farms

    DEFF Research Database (Denmark)

    Petersen, Kristian R.; Madsen, Erik Skov; Bilberg, Arne

    The offshore wind industry is booming and larger, more efficient wind-turbines have constantly been introduced into the market. However, research within the field of the operation and maintenance (O&M) of offshore wind farms is limited as the field is still immature. In this paper, two current ma...... maintenance models - RCM and TPM - are discussed in this context. Furthermore, through a case study, the paper looks into Modularization and SSLP, as these concepts can be utilized to optimize maintenance. This is a new approach for the offshore wind industry....

  6. ICD Complex Operations and Maintenance Plan

    Energy Technology Data Exchange (ETDEWEB)

    Gibson, P. L.

    2007-06-25

    This Operations and Maintenance (O&M) Plan describes how the Idaho National Laboratory (INL) conducts operations, winterization, and startup of the Idaho CERCLA Disposal Facility (ICDF) Complex. The ICDF Complex is the centralized INL facility responsible for the receipt, storage, treatment (as necessary), and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation waste.

  7. Demonstration of ITER Operational Scenarios on DIII-D

    International Nuclear Information System (INIS)

    Doyle, E.J.; Budny, R.V.; DeBoo, J.C.; Ferron, J.R.; Jackson, G.L.; Luce, T.C.; Murakami, M.; Osborne, T.H.; Park, J.; Politzer, P.A.; Reimerdes, H.; Casper, T.A.; Challis, C.D.; Groebner, R.J.; Holcomb, C.T.; Hyatt, A.W.; La Haye, R.J.; McKee, G.R.; Petrie, T.W.; Petty, C.C.; Rhodes, T.L.; Shafer, M.W.; Snyder, P.B.; Strait, E.J; Wade, M.R.; Wang, G.; West, W.P.; Zeng, L.

    2008-01-01

    The DIII-D program has recently initiated an effort to provide suitably scaled experimental evaluations of four primary ITER operational scenarios. New and unique features of this work are that the plasmas incorporate essential features of the ITER scenarios and anticipated operating characteristics; e.g., the plasma cross-section, aspect ratio and value of I/aB of the DIII-D discharges match the ITER design, with size reduced by a factor of 3.7. Key aspects of all four scenarios, such as target values for β N and H 98 , have been replicated successfully on DIII-D, providing an improved and unified physics basis for transport and stability modeling, as well as for performance extrapolation to ITER. In all four scenarios normalized performance equals or closely approaches that required to realize the physics and technology goals of ITER, and projections of the DIII-D discharges are consistent with ITER achieving its goals of (ge) 400 MW of fusion power production and Q (ge) 10. These studies also address many of the key physics issues related to the ITER design, including the L-H transition power threshold, the size of ELMs, pedestal parameter scaling, the impact of tearing modes on confinement and disruptivity, beta limits and the required capabilities of the plasma control system. An example of direct influence on the ITER design from this work is a modification of the specified operating range in internal inductance at 15 MA for the poloidal field coil set, based on observations that the measured inductance in the baseline scenario case lay outside the original ITER specification

  8. The ITER Neutral Beam Test Facility towards SPIDER operation

    Science.gov (United States)

    Toigo, V.; Dal Bello, S.; Gaio, E.; Luchetta, A.; Pasqualotto, R.; Zaccaria, P.; Bigi, M.; Chitarin, G.; Marcuzzi, D.; Pomaro, N.; Serianni, G.; Agostinetti, P.; Agostini, M.; Antoni, V.; Aprile, D.; Baltador, C.; Barbisan, M.; Battistella, M.; Boldrin, M.; Brombin, M.; Dalla Palma, M.; De Lorenzi, A.; Delogu, R.; De Muri, M.; Fellin, F.; Ferro, A.; Gambetta, G.; Grando, L.; Jain, P.; Maistrello, A.; Manduchi, G.; Marconato, N.; Pavei, M.; Peruzzo, S.; Pilan, N.; Pimazzoni, A.; Piovan, R.; Recchia, M.; Rizzolo, A.; Sartori, E.; Siragusa, M.; Spada, E.; Spagnolo, S.; Spolaore, M.; Taliercio, C.; Valente, M.; Veltri, P.; Zamengo, A.; Zaniol, B.; Zanotto, L.; Zaupa, M.; Boilson, D.; Graceffa, J.; Svensson, L.; Schunke, B.; Decamps, H.; Urbani, M.; Kushwah, M.; Chareyre, J.; Singh, M.; Bonicelli, T.; Agarici, G.; Garbuglia, A.; Masiello, A.; Paolucci, F.; Simon, M.; Bailly-Maitre, L.; Bragulat, E.; Gomez, G.; Gutierrez, D.; Mico, G.; Moreno, J.-F.; Pilard, V.; Chakraborty, A.; Baruah, U.; Rotti, C.; Patel, H.; Nagaraju, M. V.; Singh, N. P.; Patel, A.; Dhola, H.; Raval, B.; Fantz, U.; Fröschle, M.; Heinemann, B.; Kraus, W.; Nocentini, R.; Riedl, R.; Schiesko, L.; Wimmer, C.; Wünderlich, D.; Cavenago, M.; Croci, G.; Gorini, G.; Rebai, M.; Muraro, A.; Tardocchi, M.; Hemsworth, R.

    2017-08-01

    SPIDER is one of two projects of the ITER Neutral Beam Test Facility under construction in Padova, Italy, at the Consorzio RFX premises. It will have a 100 keV beam source with a full-size prototype of the radiofrequency ion source for the ITER neutral beam injector (NBI) and also, similar to the ITER diagnostic neutral beam, it is designed to operate with a pulse length of up to 3600 s, featuring an ITER-like magnetic filter field configuration (for high extraction of negative ions) and caesium oven (for high production of negative ions) layout as well as a wide set of diagnostics. These features will allow a reproduction of the ion source operation in ITER, which cannot be done in any other existing test facility. SPIDER realization is well advanced and the first operation is expected at the beginning of 2018, with the mission of achieving the ITER heating and diagnostic NBI ion source requirements and of improving its performance in terms of reliability and availability. This paper mainly focuses on the preparation of the first SPIDER operations—integration and testing of SPIDER components, completion and implementation of diagnostics and control and formulation of operation and research plan, based on a staged strategy.

  9. Demonstration of ITER operational scenarios on DIII-D

    International Nuclear Information System (INIS)

    Doyle, E.J.; DeBoo, J.C.; Ferron, J.R.; Jackson, G.L.; Luce, T.C.; Osborne, T.H.; Politzer, P.A.; Groebner, R.J.; Hyatt, A.W.; La Haye, R.J.; Petrie, T.W.; Petty, C.C.; Murakami, M.; Park, J.-M.; Reimerdes, H.; Budny, R.V.; Casper, T.A.; Holcomb, C.T.; Challis, C.D.; McKee, G.R.

    2010-01-01

    The DIII-D programme has recently initiated an effort to provide suitably scaled experimental evaluations of four primary ITER operational scenarios. New and unique features of this work are that the plasmas incorporate essential features of the ITER scenarios and anticipated operating characteristics; e.g. the plasma cross-section, aspect ratio and value of I/aB of the DIII-D discharges match the ITER design, with size reduced by a factor of 3.7. Key aspects of all four scenarios, such as target values for β N and H 98 , have been replicated successfully on DIII-D, providing an improved and unified physics basis for transport and stability modelling, as well as for performance extrapolation to ITER. In all four scenarios, normalized performance equals or closely approaches that required to realize the physics and technology goals of ITER, and projections of the DIII-D discharges are consistent with ITER achieving its goals of ≥400 MW of fusion power production and Q ≥ 10. These studies also address many of the key physics issues related to the ITER design, including the L-H transition power threshold, the size of edge localized modes, pedestal parameter scaling, the impact of tearing modes on confinement and disruptivity, beta limits and the required capabilities of the plasma control system. An example of direct influence on the ITER design from this work is a modification of the physics requirements for the poloidal field coil set at 15 MA, based on observations that the inductance in the baseline scenario case evolves to a value that lies outside the original ITER specification.

  10. EHV network operation, maintenance, organization and training

    Energy Technology Data Exchange (ETDEWEB)

    Gravier, J P [Electricite de France (EDF), 75 - Paris (France)

    1994-12-31

    The service interruptions of electricity have an ever increasing social and industrial impact, it is thus fundamental to operate the network to its best level of performances. To face these changing conditions, Electricite de France has consequently adapted its strategy to improve its organization for maintenance and operation, clarify the operation procedures and give further training to the staff. This work presents the above mentioned issues. (author) 2 figs.

  11. Safety of nuclear operation and maintenance

    International Nuclear Information System (INIS)

    Mori, M.; Nitta, T.; Sakai, K.

    1994-01-01

    The Kansai Electric Power Co. Inc.(Kansai EPC) aims to pursue a high quality and highly reliable operation in nuclear power generation in order to ensure safety by reducing the risk of accidents and win the confidence from the society and the public. It is emphasised that in order to realize this aim manufacturers and contractors cooperate with each other in performing high quality maintenance through plant lifetime maintenance system. TQC (Total Quality Control) activity enhances the motivation for each individual to have a quality-oriented mind and cultivate the safety culture. Under the lifetime employment practice, Kansai EPC and maintenance contractors can conduct systematic education and training, and the Maintenance Training Center helps to make it effective. 6 figs

  12. Steam generator operation and maintenance

    International Nuclear Information System (INIS)

    Lee, C.K.

    2004-01-01

    Corrosion of steam generator tube has resulted in the need for extensive repair and replacement of steam generators. Over the past two decades, steam generator problems in the United States were viewed to be one of the most significant contributor to lost generation in operating PWR plants. When the SGOG-I (Steam Generator Owners Groups) was formed in early 1977, denting was responsible for almost 90% of the tube plugging. By the end of 1982, this figure was reduced to less than 2%. During the existence of SGOG-II (from 1982 to 1986), IGA/SCC (lntergranular Attack/Stress Corrosion Cracking) in the tube sheet, primary side SCC, pitting, and fretting surfaced as the primary causes of tube degradation. Although significant process has been made with wastage and denting, the utilities experience shows that the percentage of reactors plugging tubes and the percentage of tubes being plugged each year has remained relatively constant. The diversity of the damage mechanisms means that no one solution is likely to resolve all problems. The task of maintaining steam generator integrity continues to be formidable and challenging. As the older problems were brought under control, many new problems emerged. SGOG-II (Steam Generator Owners Group program from 1982 to 1986) has focused on these problem areas such as tube stress corrosion cracking (SCC) and intergranular attack (IGA) in the open tube sheet crevice, primary side tube cracking, pitting in the lower span, and tube fretting in preheated section and anti-vibration bar (AVB) locations. Primary Water Stress Corrosion Cracking (PWSCC) in the tube to tubesheet roll transition has been a wide spread problem in the Recirculation Steam Generators (RSG) during this period. Although significant progress has been made in resolving this problem, considerable work still remains. One typical problem in the Once Through Steam Generator (OTSG) was the tube support plate broached hole fouling which affects the OTSG steam generating

  13. Software design of the hybrid robot machine for ITER vacuum vessel assembly and maintenance

    International Nuclear Information System (INIS)

    Li, Ming; Wu, Huapeng; Handroos, Heikki; Yang, Guangyou

    2013-01-01

    A specific software design is elaborated in this paper for the hybrid robot machine used for the ITER vacuum vessel (VV) assembly and maintenance. In order to provide the multi-machining-function as well as the complicated, flexible and customizable GUI designing satisfying the non-standardized VV assembly process in one hand, and in another hand guarantee the stringent machining precision in the real-time motion control of robot machine, a client–server-control software architecture is proposed, which separates the user interaction, data communication and robot control implementation into different software layers. Correspondingly, three particular application protocols upon the TCP/IP are designed to transmit the data, command and status between the client and the server so as to deal with the abundant data streaming in the software. In order not to be affected by the graphic user interface (GUI) modification process in the future experiment in VV assembly working field, the real-time control system is realized as a stand-alone module in the architecture to guarantee the controlling performance of the robot machine. After completing the software development, a milling operation is tested on the robot machine, and the result demonstrates that both the specific GUI operability and the real-time motion control performance could be guaranteed adequately in the software design

  14. Software design of the hybrid robot machine for ITER vacuum vessel assembly and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Li, Ming, E-mail: Ming.Li@lut.fi [Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland); Wu, Huapeng; Handroos, Heikki [Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland); Yang, Guangyou [School of Mechanical Engineering, Hubei University of Technology, Wuhan (China)

    2013-10-15

    A specific software design is elaborated in this paper for the hybrid robot machine used for the ITER vacuum vessel (VV) assembly and maintenance. In order to provide the multi-machining-function as well as the complicated, flexible and customizable GUI designing satisfying the non-standardized VV assembly process in one hand, and in another hand guarantee the stringent machining precision in the real-time motion control of robot machine, a client–server-control software architecture is proposed, which separates the user interaction, data communication and robot control implementation into different software layers. Correspondingly, three particular application protocols upon the TCP/IP are designed to transmit the data, command and status between the client and the server so as to deal with the abundant data streaming in the software. In order not to be affected by the graphic user interface (GUI) modification process in the future experiment in VV assembly working field, the real-time control system is realized as a stand-alone module in the architecture to guarantee the controlling performance of the robot machine. After completing the software development, a milling operation is tested on the robot machine, and the result demonstrates that both the specific GUI operability and the real-time motion control performance could be guaranteed adequately in the software design.

  15. Setting up and managing a remote maintenance operation for fusion

    International Nuclear Information System (INIS)

    Haist, Bernhard

    2008-01-01

    Trying to set up and manage a remote maintenance operation for a thermonuclear fusion reactor is a complex undertaking. There are many problems and challenges which need addressing. This paper tries to guide the reader through this process by composing a list of generic problems and by analysing possible solutions. The first challenge before setting up a remote maintenance operation for a fusion reactor is the systematic analysis of all the remote handling requirements. Based upon this the remote handling concept, including facility layout and equipment, can be defined. The following aspects have to be considered and incorporated into the remote handling concept: - Remote handling task development. - Remote handling task logistics and resource management. - Command, control and human-machine interface system. - Viewing and camera systems. - Virtual reality and Augmented Reality software. - Automatic path planning and collision avoidance. - Remote transfer of heavy loads. - Maintainability of RH equipment. - Reliability, redundant systems and safety. - Rationalisation and modularity in both hardware and software. - Recovery from failure modes. - Condition monitoring and fault detection/prediction. - Ability to deal with unforeseen problems. Oxford Technologies Ltd. has a proven track record in setting up and running the Remote Handling group at the JET Joint Undertaking in Culham, UK. Based on the unique experience gained at JET, Oxford Technologies Ltd. also developed the current design and remote handling concept of the ITER Hot Cell during a study in 2004. Examples of both the JET remote handling experience and the ITER Hot Cell design and layout are given throughout this paper

  16. Setting up and managing a remote maintenance operation for fusion

    International Nuclear Information System (INIS)

    Haist, B.

    2007-01-01

    Trying to set up and manage a remote maintenance operation for a thermonuclear fusion reactor is a complex undertaking. There are many problems and challenges which need addressing. This paper tries to guide the reader through this process by composing a list of generic problems and by analysing possible solutions. The first challenge before setting up a remote maintenance operation for a fusion reactor is the systematic analysis of all the remote handling requirements. Based upon this the remote handling concept, including facility layout and equipment, can be defined. The following aspects have to be considered and incorporated into the remote handling concept: - Remote handling task development - Remote handling task logistics and resource management - Command, control and human-machine interface system - Viewing and camera systems - Virtual Reality and Augmented Reality software - Automatic path planning and collision avoidance - Remote transfer of heavy loads - Maintainability of RH Equipment - Reliability, redundant systems and safety - Rationalisation and modularity in both hardware and software - Recovery from failure modes - Condition monitoring and fault detection/prediction - Ability to deal with unforeseen problems Oxford Technologies Ltd has a proven track record in setting up and running the Remote Handling group at the JET Joint Undertaking in Culham, UK. Based on the unique experience gained at JET, Oxford Technologies Ltd also developed the current design and remote handling concept of the ITER Hot Cell during a study in 2004. Examples of both the JET Remote Handling experience and the ITER Hot Cell design and layout are given throughout this paper. (orig.)

  17. Setting up and managing a remote maintenance operation for fusion

    Energy Technology Data Exchange (ETDEWEB)

    Haist, Bernhard [Oxford Technologies Ltd., 7 Nuffield Way, Abingdon, Oxon OX14 1RJ (United Kingdom)], E-mail: Bernhard.Haist@oxfordtechnologies.co.uk

    2008-12-15

    Trying to set up and manage a remote maintenance operation for a thermonuclear fusion reactor is a complex undertaking. There are many problems and challenges which need addressing. This paper tries to guide the reader through this process by composing a list of generic problems and by analysing possible solutions. The first challenge before setting up a remote maintenance operation for a fusion reactor is the systematic analysis of all the remote handling requirements. Based upon this the remote handling concept, including facility layout and equipment, can be defined. The following aspects have to be considered and incorporated into the remote handling concept: - Remote handling task development. - Remote handling task logistics and resource management. - Command, control and human-machine interface system. - Viewing and camera systems. - Virtual reality and Augmented Reality software. - Automatic path planning and collision avoidance. - Remote transfer of heavy loads. - Maintainability of RH equipment. - Reliability, redundant systems and safety. - Rationalisation and modularity in both hardware and software. - Recovery from failure modes. - Condition monitoring and fault detection/prediction. - Ability to deal with unforeseen problems. Oxford Technologies Ltd. has a proven track record in setting up and running the Remote Handling group at the JET Joint Undertaking in Culham, UK. Based on the unique experience gained at JET, Oxford Technologies Ltd. also developed the current design and remote handling concept of the ITER Hot Cell during a study in 2004. Examples of both the JET remote handling experience and the ITER Hot Cell design and layout are given throughout this paper.

  18. Chatter suppression methods of a robot machine for ITER vacuum vessel assembly and maintenance

    International Nuclear Information System (INIS)

    Wu, Huapeng; Wang, Yongbo; Li, Ming; Al-Saedi, Mazin; Handroos, Heikki

    2014-01-01

    Highlights: •A redundant 10-DOF serial-parallel hybrid robot for ITER assembly and maintains is presented. •A dynamic model of the robot is developed. •A feedback and feedforward controller is presented to suppress machining vibration of the robot. -- Abstract: In the process of assembly and maintenance of ITER vacuum vessel (ITER VV), various machining tasks including threading, milling, welding-defects cutting and flexible hose boring are required to be performed from inside of ITER VV by on-site machining tools. Robot machine is a promising option for these tasks, but great chatter (machine vibration) would happen in the machining process. The chatter vibration will deteriorate the robot accuracy and surface quality, and even cause some damages on the end-effector tools and the robot structure itself. This paper introduces two vibration control methods, one is passive and another is active vibration control. For the passive vibration control, a parallel mechanism is presented to increase the stiffness of robot machine; for the active vibration control, a hybrid control method combining feedforward controller and nonlinear feedback controller is introduced for chatter suppression. A dynamic model and its chatter vibration phenomena of a hybrid robot is demonstrated. Simulation results are given based on the proposed hybrid robot machine which is developed for the ITER VV assembly and maintenance

  19. Chatter suppression methods of a robot machine for ITER vacuum vessel assembly and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Huapeng; Wang, Yongbo, E-mail: yongbo.wang@lut.fi; Li, Ming; Al-Saedi, Mazin; Handroos, Heikki

    2014-10-15

    Highlights: •A redundant 10-DOF serial-parallel hybrid robot for ITER assembly and maintains is presented. •A dynamic model of the robot is developed. •A feedback and feedforward controller is presented to suppress machining vibration of the robot. -- Abstract: In the process of assembly and maintenance of ITER vacuum vessel (ITER VV), various machining tasks including threading, milling, welding-defects cutting and flexible hose boring are required to be performed from inside of ITER VV by on-site machining tools. Robot machine is a promising option for these tasks, but great chatter (machine vibration) would happen in the machining process. The chatter vibration will deteriorate the robot accuracy and surface quality, and even cause some damages on the end-effector tools and the robot structure itself. This paper introduces two vibration control methods, one is passive and another is active vibration control. For the passive vibration control, a parallel mechanism is presented to increase the stiffness of robot machine; for the active vibration control, a hybrid control method combining feedforward controller and nonlinear feedback controller is introduced for chatter suppression. A dynamic model and its chatter vibration phenomena of a hybrid robot is demonstrated. Simulation results are given based on the proposed hybrid robot machine which is developed for the ITER VV assembly and maintenance.

  20. Survey of Operators Knowledge of Operation and Maintenance of ...

    African Journals Online (AJOL)

    Result showed that the machine failures encountered during operations were as a result of poor management, inadequate maintenance practices, and lack of spare parts, obsoleteness, overloading, careless operations and poor storage of machine after use. Recommendations were therefore given to improve the operation ...

  1. Maintenance Operations Degradation of Airfield Pavement Markings

    Science.gov (United States)

    2012-03-01

    DISTRIBUTION STATEMENT A. APPROVED FOR PUBLIC RELEASE; DISTRIBUTION UNLIMITED The views expressed in this article are those of the author and...DISTRIBUTION STATEMENT A. APPROVED FOR PUBLIC RELEASE; DISTRIBUTION UNLIMITED AFIT/GEM/ENV/12-M09 MAINTENANCE OPERATIONS DEGRADATION OF...placement, color, and style (Federal Aviation Adminstration (FAA), 2010). However, regulations and standards do not make good asset management plans

  2. Davis PV plant operation and maintenance manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This operation and maintenance manual contains the information necessary to run the Photovoltaics for Utility Scale Applications (PVUSA) test facility in Davis, California. References to more specific information available in drawings, data sheets, files, or vendor manuals are included. The PVUSA is a national cooperative research and demonstration program formed in 1987 to assess the potential of utility scale photovoltaic systems.

  3. Operation and maintenance of the technical installations in buildings

    DEFF Research Database (Denmark)

    Nielsen, O.(red.)

    The report contains twelve papers from a seminar on operation and maintenance, held at the Danish Building Research Institute in October 1976. The papers deal, among other things, with dimensioning and balancing of pipesystems, design of ventilating systems for adequate operation and maintenance,......, cost and quality in maintenance, maintenance service companies, as well as organization and training for building services maintenance....

  4. Experience in operation and maintenance of PWRs

    International Nuclear Information System (INIS)

    Broecker, H.; Schomer, E.

    1987-01-01

    At present there are 10 PWRs in operation, most of them built on turnkey basis by KWU. The availability of West German PWRs amounted to 84.7% on average for the period from 1982-86. The good operating results are attributable to the following: 1. Sophiticated design and layout of the plant with good accessibility to the primary system even during operation. 2. Reliable performance of plant and components as result of extensive quality assurance. 3. Well-organized and highly qualified operating personnel. 4. Inservice inspection and preventive maintenance. 5. Good information feedback system. (Liu)

  5. Projection-iteration methods for solving nonlinear operator equations

    International Nuclear Information System (INIS)

    Nguyen Minh Chuong; Tran thi Lan Anh; Tran Quoc Binh

    1989-09-01

    In this paper, the authors investigate a nonlinear operator equation in uniformly convex Banach spaces as in metric spaces by using stationary and nonstationary generalized projection-iteration methods. Convergence theorems in the strong and weak sense were established. (author). 7 refs

  6. e-Learning Application for Machine Maintenance Process using Iterative Method in XYZ Company

    Science.gov (United States)

    Nurunisa, Suaidah; Kurniawati, Amelia; Pramuditya Soesanto, Rayinda; Yunan Kurnia Septo Hediyanto, Umar

    2016-02-01

    XYZ Company is a company based on manufacturing part for airplane, one of the machine that is categorized as key facility in the company is Millac 5H6P. As a key facility, the machines should be assured to work well and in peak condition, therefore, maintenance process is needed periodically. From the data gathering, it is known that there are lack of competency from the maintenance staff to maintain different type of machine which is not assigned by the supervisor, this indicate that knowledge which possessed by maintenance staff are uneven. The purpose of this research is to create knowledge-based e-learning application as a realization from externalization process in knowledge transfer process to maintain the machine. The application feature are adjusted for maintenance purpose using e-learning framework for maintenance process, the content of the application support multimedia for learning purpose. QFD is used in this research to understand the needs from user. The application is built using moodle with iterative method for software development cycle and UML Diagram. The result from this research is e-learning application as sharing knowledge media for maintenance staff in the company. From the test, it is known that the application make maintenance staff easy to understand the competencies.

  7. Analysis of human-in-the-loop tele-operated maintenance inspection tasks using VR

    International Nuclear Information System (INIS)

    Boessenkool, H.; Abbink, D.A.; Heemskerk, C.J.M.; Steinbuch, M.; Baar, M.R. de; Wildenbeest, J.G.W.; Ronden, D.; Koning, J.F.

    2013-01-01

    Highlights: ► Execution of tele-operated inspection tasks for ITER maintenance was analyzed. ► Human factors experiments using Virtual Reality showed to be a valuable approach. ► A large variation in time performance and number of collisions was found. ► Results indicate significant room for improvement for teleoperated free space tasks. ► A promising solution is haptic shared control: assist operator with guiding forces. -- Abstract: One of the challenges in future fusion plants such as ITER is the remote maintenance of the plant. Foreseen human-in-the-loop tele-operation is characterized by limited visual and haptic feedback from the environment, which results in degraded task performance and increased operator workload. For improved tele-operated task performance it is required to get insight in the expected tasks and problems during maintenance at ITER. By means of an exploratory human factor experiment, this paper analyses problems and bottlenecks during the execution of foreseen tele-operated maintenance at ITER, identifying most promising areas of improvement. The focus of this paper is on free space (sub)tasks where contact with the environment needs to be avoided. A group of 5 subjects was asked to carry-out an ITER related free space task (visual inspection), using a six degree of freedom master device connected to a simulated hot cell environment. The results show large variation in time performance between subjects and an increasing number of collisions for more difficult tasks, indicating room for improvement for free space (sub)tasks. The results will be used in future research on the haptic guidance strategies in the ITER Remote Handling framework

  8. Analysis of human-in-the-loop tele-operated maintenance inspection tasks using VR

    Energy Technology Data Exchange (ETDEWEB)

    Boessenkool, H., E-mail: h.boessenkool@differ.nl [FOM Institute DIFFER (Dutch Institute for Fundamental Energy Research), Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, PO Box 1207, 3430 BE Nieuwegein (Netherlands); Eindhoven University of Technology, Department of Mechanical Engineering, Dynamics and Control Group, PO Box 513, 5600 MB Eindhoven (Netherlands); Abbink, D.A. [Delft University of Technology, Faculty of 3mE, BioMechanical Engineering Department, Mekelweg 2, 2628 CD Delft (Netherlands); Heemskerk, C.J.M. [Heemskerk Innovative Technology B.V., Jonckerweg 12, 2201 DZ Noordwijk (Netherlands); Steinbuch, M. [Eindhoven University of Technology, Department of Mechanical Engineering, Dynamics and Control Group, PO Box 513, 5600 MB Eindhoven (Netherlands); Baar, M.R. de [FOM Institute DIFFER (Dutch Institute for Fundamental Energy Research), Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, PO Box 1207, 3430 BE Nieuwegein (Netherlands); Eindhoven University of Technology, Department of Mechanical Engineering, Dynamics and Control Group, PO Box 513, 5600 MB Eindhoven (Netherlands); Wildenbeest, J.G.W. [Delft University of Technology, Faculty of 3mE, BioMechanical Engineering Department, Mekelweg 2, 2628 CD Delft (Netherlands); Heemskerk Innovative Technology B.V., Jonckerweg 12, 2201 DZ Noordwijk (Netherlands); Ronden, D. [FOM Institute DIFFER (Dutch Institute for Fundamental Energy Research), Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, PO Box 1207, 3430 BE Nieuwegein (Netherlands); Koning, J.F. [Heemskerk Innovative Technology B.V., Jonckerweg 12, 2201 DZ Noordwijk (Netherlands)

    2013-10-15

    Highlights: ► Execution of tele-operated inspection tasks for ITER maintenance was analyzed. ► Human factors experiments using Virtual Reality showed to be a valuable approach. ► A large variation in time performance and number of collisions was found. ► Results indicate significant room for improvement for teleoperated free space tasks. ► A promising solution is haptic shared control: assist operator with guiding forces. -- Abstract: One of the challenges in future fusion plants such as ITER is the remote maintenance of the plant. Foreseen human-in-the-loop tele-operation is characterized by limited visual and haptic feedback from the environment, which results in degraded task performance and increased operator workload. For improved tele-operated task performance it is required to get insight in the expected tasks and problems during maintenance at ITER. By means of an exploratory human factor experiment, this paper analyses problems and bottlenecks during the execution of foreseen tele-operated maintenance at ITER, identifying most promising areas of improvement. The focus of this paper is on free space (sub)tasks where contact with the environment needs to be avoided. A group of 5 subjects was asked to carry-out an ITER related free space task (visual inspection), using a six degree of freedom master device connected to a simulated hot cell environment. The results show large variation in time performance between subjects and an increasing number of collisions for more difficult tasks, indicating room for improvement for free space (sub)tasks. The results will be used in future research on the haptic guidance strategies in the ITER Remote Handling framework.

  9. Quantification and disposal of radioactive waste from ITER operation

    International Nuclear Information System (INIS)

    Olsson, G.; Devell, L.; Johnsson, B.; Gulden, W.

    1991-01-01

    The work on the safety and environment for the Next European Torus (NET) is being performed within the European Fusion Technology Safety and Environment Programme by the NET team and under NET contracts. In the area of NET-oriented investigations concerning waste management and disposal, Studsvik is concentrating on the operational waste from both NET and ITER (International Thermonuclear Experimental Reactor). This paper gives a characterization and quantification of the radioactive waste generated from the operation of ITER during the Physics Phase, and from the replacement of all blanket segments (European shielding blanket option) at the end of the Physics Phase after an integrated first-wall loading of 0.03 MWy/m 2 . The total activity contents and volumes of packaged waste from the Physics Phase operation and from the blanket replacement are estimated. The waste volume from replacement of the shielding blanket segments of ITER is considerably larger than estimated in earlier calculations for NET due to the fact that the ITER conceptual design includes more of the stell shielding in the removable segments. The waste handling and disposal are described using existing Swedish and German concepts for similar waste categories from nuclear fission reactors. This includes the choice of suitable packagings, intermediate storage time for cooling, and type of repository for final disposal. Some typical cost figures for waste handling are also presented. (orig.)

  10. Guidelines for safe process operations and maintenance

    CERN Document Server

    2010-01-01

    First-line managers have to maintain the integrity of facilities, control manufacturing processes, and handle unusual or emergency situations, as well as respond to the pressures of production demand. On a daily basis, they are closest to the operating personnel who may be injured by a process accident, and they are in the best position to spot problem conditions and to act to contain them. This book offers these managers ""how-to"" information on process safety management program execution in the operations and maintenance departments, recommending technical and administrative process safety

  11. Primary design and operation analysis of ITER air transfer system

    International Nuclear Information System (INIS)

    Wang Haitian; Li Ge; Qin Shijun

    2010-01-01

    Air transfer system (ATS) is a remote handling transfer, which can work in the nuclear radiation environment and can be driven by the electricity fully. Its motion power is provided by several servo motors. The remote control technology of ATS, which is China taking part in the plan of international Tokamak experimental reactor (ITER) and grasping this technology, is one of key technologies of ITER. The remote handling technology can lay the foundation for developing demonstration nuclear fusion power plant in China on self-reliance. Because there is gamma irradiation and hazard material in these ITER parts, all required maintenance of port plugs and inner components are been transmitted by ATS. The pick-up or drop-off these components are completed by means of a remotely controlled TCS system between the Vacuum Vessel and the Hot Cell through the bridge-gallery. Tokamak building includes three floors, including upper port, equatorial port and lower port, linked by a lift. According to each port level configuration and safety requirement, the radius of curvature with ATS trajectory is optimized, and a trajectory of each level is determined by positioned guidance beacons. At last, the results of computer aided design (CAD) show single trajectory guidance of ATS in each level is available. (authors)

  12. Artificial intelligence applications for operation and maintenance

    International Nuclear Information System (INIS)

    Itoh, M.; Tai, I.; Monta, K.; Sekimizu, K.

    1987-01-01

    A nuclear power plant as a typical man-machine system of the modern industry needs an efficient human window through which operators can observe every necessary detail of the plant for its safe and reliable operation. Much efforts have been devoted to the development of the computerized operator support systems (COSS). Recent development of artificial intelligence (AI) seems to offer new possibility to strengthen the performance of the COSS such as more powerful diagnosis and procedure synthesis and user friendly man-machine interfaces. From this point of view, a national project of Advanced Man-Machine System Development for Nuclear Power Plants has been carried out. Artificial intelligence application to nuclear power plant operation and maintenance is also selected as a major theme for the promotion of research and development on frontiers in the recently revised long term national program for development and utilization of nuclear energy in JAPAN

  13. Manufacturing and maintenance technologies developed for a thick-wall structure of the ITER vacuum vessel

    International Nuclear Information System (INIS)

    Onozuka, M.; Alfile, J.P.; Aubert, Ph.; Dagenais, J.-F.; Grebennikov, D.; Ioki, K.; Jones, L.; Koizumi, K.; Krylov, V.; Maslakowski, J.; Nakahira, M.; Nelson, B.; Punshon, C.; Roy, O.; Schreck, G.

    2001-01-01

    Development of welding, cutting and non-destructive testing (NDT) techniques, and development of remotized systems have been carried out for on-site manufacturing and maintenance of the thick-wall structure of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel (VV). Conventional techniques, including tungsten inert gas welding, plasma cutting, and ultrasonic inspection, have been improved and optimized for the application to thick austenitic stainless steel plates. In addition, advanced methods have been investigated, including reduced-pressure electron-beam and multi-pass neodymium-doped yttrium aluminum garnet (NdYAG) laser welding, NdYAG laser cutting, and electro-magnetic acoustic transducer inspection, to improve cost and technical performance. Two types of remotized systems with different payloads have been investigated and one of them has been fabricated and demonstrated in field joint welding, cutting, and NDT tests on test mockups and full-scale ITER VV sector models. The progress and results of this development to date provide a high level of confidence that the manufacturing and maintenance of the ITER VV is feasible

  14. Manufacturing and maintenance technologies developed for a thick-wall structure of the ITER vacuum vessel

    Energy Technology Data Exchange (ETDEWEB)

    Onozuka, M. E-mail: onozukm@itereu.de; Alfile, J.P.; Aubert, Ph.; Dagenais, J.-F.; Grebennikov, D.; Ioki, K.; Jones, L.; Koizumi, K.; Krylov, V.; Maslakowski, J.; Nakahira, M.; Nelson, B.; Punshon, C.; Roy, O.; Schreck, G

    2001-09-01

    Development of welding, cutting and non-destructive testing (NDT) techniques, and development of remotized systems have been carried out for on-site manufacturing and maintenance of the thick-wall structure of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel (VV). Conventional techniques, including tungsten inert gas welding, plasma cutting, and ultrasonic inspection, have been improved and optimized for the application to thick austenitic stainless steel plates. In addition, advanced methods have been investigated, including reduced-pressure electron-beam and multi-pass neodymium-doped yttrium aluminum garnet (NdYAG) laser welding, NdYAG laser cutting, and electro-magnetic acoustic transducer inspection, to improve cost and technical performance. Two types of remotized systems with different payloads have been investigated and one of them has been fabricated and demonstrated in field joint welding, cutting, and NDT tests on test mockups and full-scale ITER VV sector models. The progress and results of this development to date provide a high level of confidence that the manufacturing and maintenance of the ITER VV is feasible.

  15. The operational challenge of remote maintenance

    International Nuclear Information System (INIS)

    Forsythe, L.

    2015-01-01

    Full text of publication follows. With the declining supply of fossil fuels that are used in power stations today, and the ongoing concern over climate change, nuclear fusion is one of the most promising options for generating large amounts of carbon-free energy in the future. Fuel supplies for fusion will be available for millions of years, with 1 kg of fusion fuel providing the same amount of energy as 10 thousand tonnes of fossil fuel. Unlike conventional fission reactors, the radioactive waste produced from fusion is short-lived, and will be safe to dispose of conventionally within 100 years. Although fusion has the huge advantage of being a carbon free energy source, there are complexities when it comes to maintaining the machine. Due to the nature of the fusion reaction, the components within the area of the reactor vacuum vessel become radioactive, which requires maintenance and modifications to be conducted remotely to protect human operators. Remote maintenance is the use of manipulators to carry out tasks in challenging or hostile environments, which would otherwise cause harm to humans. Remote handling slave manipulators do the work of a human by mimicking the movements from a master robotic manipulator that is controlled by a human operator. This means that remote handling can be used in many other areas other too, such as space; fission power plants; sub-sea; and nuclear material handling or in adverse environments such as: low or high temperature; chemically contaminated; combustible and low oxygen environments. Remote maintenance requires specialist engineers to take into consideration many aspects normally taken for granted when carrying out a task manually. Constraints such as the space around us; viewing and lighting; the human body's dexterity and flexibility; the weight and centre of gravity of tools and components, and how we securely grip and handle them; and access to fixings and fastenings. All these are factors that require careful

  16. Parametric analysis and operational performance of EDA-ITER

    International Nuclear Information System (INIS)

    Murakami, Yoshiki; Tsunematsu, Toshihide; Fujieda, Hirobumi.

    1994-06-01

    Confinement capability of EDA-ITER is investigated by using a 0-D model based on CDA physics design guidelines. Confinement enhancement factor (H-factor) is evaluated and required fusion power (P FUS ) for the ignition is calculated. It is found that ignition is possible in H-mode plasma (H=2) when helium accumulation (He) is 10% and P FUS ≥ 1 GW. For Rebut-Lallia scaling law, L-mode (H=1) ignition is possible when P FUS ≥ 3 GW. The required fusion power is, however, more than 4 GW even in H-mode plasmas when the helium accumulation is 20%. Therefore, it is an important future work to study how much helium accumulates in a burning plasma. Capability of steady-state mode operation is also investigated. Required current-drive power for H-mode plasma is about 140 MW when He=10% and the fusion gain Q is more than 5. If the enhanced confinement (H∼3) in high safety factor region (q∼5) can be adoptable, steady-state operation with Q>10 is possible and the required current-drive power is about 60 MW. In spite of the larger fusion power, the divertor heat load of EDA-ITER calculated by scaling models is comparable or smaller than that of CDA-ITER due to the longer connection length. Thermal instability of EDA-ITER is also investigated. The growth time is about 15 s for ITER89 power scaling law. Fusion power excursion is investigated in very preliminary way. It is found that the power rises from 1.5 GW to 3 GW in about 100 s if there is no control. Although this instability could be stabilized by beta limit or helium accumulation effect, it is an important future work since it may cause severe problem. (author)

  17. Rail deployment and storage procedure and test for ITER blanket remote maintenance

    International Nuclear Information System (INIS)

    Kakudate, S.; Shibanuma, K.

    2003-01-01

    A concept of rail-mounted vehicle manipulator system has been developed to apply to the maintenance of the ITER blanket composed of ∼400 modules in the vacuum vessel. The most critical issue of the vehicle manipulator system is the feasibility of the deployment and storage of the articulated rail, composed of eight rail links without any driving mechanism in the joints. To solve this issue, a new driving mechanism and procedure for the rail deployment and storage has been proposed, taking account of the repeated operation of the multi-rail links deployed and stored in the same kinematical manner. The new driving mechanism, which is different from those of a usual articulated manipulator or 'articulated boom' equipped with actuators in every joint for movement, is composed of three external mechanisms installed outside the articulated rail, i.e. a vehicle traveling mechanism as main driver and two auxiliary driving mechanisms. A simplified synchronized control of three driving mechanisms has also been proposed, including 'torque-limit control' for suppression of the overload of the mechanisms. These proposals have been tested using a full-scale vehicle manipulator system, in order to demonstrate the proof of principle for rail deployment and storage. As a result, the articulated rail has been successfully deployed and stored within 6 h each, less than the target of 8 h, by means of the three external driving mechanisms and the proposed synchronized control. In addition, the overload caused by an unexpected mismatch of the synchronized control of three driving mechanisms has also been successfully suppressed less than the rated torque by the proposed 'torque-limit control'. It is therefore concluded that the feasibility of the rail deployment and storage of the vehicle manipulator system has been demonstrated

  18. Operations and maintenance costs - Selected observations

    International Nuclear Information System (INIS)

    Kirk, M.W.

    1991-01-01

    The operations and maintenance (O and M) costs associated with nuclear power plants have been rising continuously over the past decade. The Nuclear Management and Resources Council (NUMARC) has undertaken an examination of this issue to determine what components of O and M costs are driven by regulatory activity. Observers from various perspectives within the nuclear industry have cited staffing, outages, training, and management structure among others as large contributors to O and M costs. NUMARC is currently analyzing utility cost data to isolate the regulatory components for further action

  19. Conceptual design of a test facility for the remote handling operations of the ITER Test Blanker Modules

    International Nuclear Information System (INIS)

    Marqueta, A.; Garcia, I.; Gomez, A.; Garcia, L.; Sedano, E.; Fernandez, I.

    2012-01-01

    Conceptual Design of a test facility for the remote handling operations of the ITER Test Blanket Modules. Conditions inside a fusion reactor are incompatible with conventional manual maintenance tasks. the same applies for ancillary equipment. As a consequence, it will become necessary to turn to remote visualization and remote handling techniques, which will have in consideration the extreme conditions, both physical and operating, of ITER. Main goal of the project has been the realization of the conceptual design for the test facility for the Test Blanket Modules of ITER and their associated systems, related to the Remote Handling operations regarding the Port Cell area. Besides the definition of the operations and the specification of the main components and ancillary systems of the TBM graphical simulation have been used for the design, verification and validation of the remote handling operations. (Author)

  20. ITER diagnostics: Maintenance and commissioning in the hot cell test bed

    International Nuclear Information System (INIS)

    Walker, C.I.; Barnsley, R.; Costley, A.E.; Gottfried, R.; Haist, B.; Itami, K.; Kondoh, T.; Loesser, G.D.; Palmer, J.; Sugie, T.; Tesini, A.; Vayakis, G.

    2005-01-01

    In-vessel diagnostic equipment in ITER integrated in six equatorial and 12 upper ports, 16 divertor cassettes and five lower ports is designed to be removed in modules and then repaired, tested and commissioned in the same location at the ITER hot cell. The repair requirements and tests on these components are described along with design features that facilitate repair. The testing establishes the repair strategy, qualifies the refurbishment work and finally checks the mechanical and diagnostic function before the return of the modules. At the hot cell, a dummy port is provided for tests of mechanical and vacuum integrity as well as commissioning of the diagnostic equipment. The scope of the hot cell maintenance and commissioning activities is summarised and an overview of the integration of the diagnostic equipment is given

  1. Depot Maintenance: Executed Workload and Maintenance Operations at DOD Depots

    Science.gov (United States)

    2017-02-03

    in turn enable testing of helicopter rotor blades. The Army has also made investments in logistics software at all of its depots. According to the...maintenance and repair of structural helicopter airframes and blades; advanced composite technologies; flight controls and control surfaces; and...level maintenance on a wide range of vehicles and other military assets, including helicopters , combat vehicles, ships, aircraft, engines, and software

  2. Development of laser cutting/welding system for remote maintenance of ITER manifold

    Energy Technology Data Exchange (ETDEWEB)

    Yamaoka, Hiroto; Tsuchiya, Kazuyuki; Awano, Toshihiko [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan); Oka, Kiyoshi [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2002-09-01

    A remote pipe cutting/welding system using a YAG laser was designed and fabricated for the maintenance of the main structural parts of ITER (International Thermonuclear Experimental Reactor), and a mock-up test carried out. The functions of this system are to cut 100A x Sch 40 pipes of SUS316L by internal access, to adjust the core gap between the as-cut pipe and new pipe, and to weld the pipes automatically. The core gap of the pipes could be decreased within the proper welding conditions by the mock-up test, and sound beads were obtained. (author)

  3. Safe operation and maintenance of research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Munsorn, S. [Reactor Operation Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok (Thailand)

    1999-10-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U{sub 3}O{sub 8}- Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  4. Safe operation and maintenance of research reactor

    International Nuclear Information System (INIS)

    Munsorn, S.

    1999-01-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U 3 O 8 - Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  5. Time parallelization of advanced operation scenario simulations of ITER plasma

    International Nuclear Information System (INIS)

    Samaddar, D; Casper, T A; Kim, S H; Houlberg, W A; Berry, L A; Elwasif, W R; Batchelor, D

    2013-01-01

    This work demonstrates that simulations of advanced burning plasma operation scenarios can be successfully parallelized in time using the parareal algorithm. CORSICA -an advanced operation scenario code for tokamak plasmas is used as a test case. This is a unique application since the parareal algorithm has so far been applied to relatively much simpler systems except for the case of turbulence. In the present application, a computational gain of an order of magnitude has been achieved which is extremely promising. A successful implementation of the Parareal algorithm to codes like CORSICA ushers in the possibility of time efficient simulations of ITER plasmas.

  6. An iterative method for nonlinear demiclosed monotone-type operators

    International Nuclear Information System (INIS)

    Chidume, C.E.

    1991-01-01

    It is proved that a well known fixed point iteration scheme which has been used for approximating solutions of certain nonlinear demiclosed monotone-type operator equations in Hilbert spaces remains applicable in real Banach spaces with property (U, α, m+1, m). These Banach spaces include the L p -spaces, p is an element of [2,∞]. An application of our results to the approximation of a solution of a certain linear operator equation in this general setting is also given. (author). 19 refs

  7. First operation experiences with ITER-FEAT model pump

    International Nuclear Information System (INIS)

    Mack, A.; Day, Chr.; Haas, H.; Murdoch, D.K.; Boissin, J.C.; Schummer, P.

    2001-01-01

    Design and manufacturing of the model cryopump for ITER-FEAT have been finished. After acceptance tests at the contractor's premises the pump was installed in the TIMO-facility which was prepared for testing the pump under ITER-FEAT relevant operating conditions. The procedures for the final acceptance tests are described. Travelling time, positioning accuracy and leak rate of the main valve are within the requirements. The heat loads to the 5 and 80 K circuits are a factor two better than the designed values. The maximum pumping speeds for H 2 , D 2 , He, Ne were measured. The value of 58 m 3 /s for D 2 is well above the contractual required value of 40 m 3 /s

  8. Iterative Repair Planning for Spacecraft Operations Using the Aspen System

    Science.gov (United States)

    Rabideau, G.; Knight, R.; Chien, S.; Fukunaga, A.; Govindjee, A.

    2000-01-01

    This paper describes the Automated Scheduling and Planning Environment (ASPEN). ASPEN encodes complex spacecraft knowledge of operability constraints, flight rules, spacecraft hardware, science experiments and operations procedures to allow for automated generation of low level spacecraft sequences. Using a technique called iterative repair, ASPEN classifies constraint violations (i.e., conflicts) and attempts to repair each by performing a planning or scheduling operation. It must reason about which conflict to resolve first and what repair method to try for the given conflict. ASPEN is currently being utilized in the development of automated planner/scheduler systems for several spacecraft, including the UFO-1 naval communications satellite and the Citizen Explorer (CX1) satellite, as well as for planetary rover operations and antenna ground systems automation. This paper focuses on the algorithm and search strategies employed by ASPEN to resolve spacecraft operations constraints, as well as the data structures for representing these constraints.

  9. Development of ITER CODAC compatible gyrotron local control system and its operation

    International Nuclear Information System (INIS)

    Ohshima, Katsumi; Oda, Yasuhisa; Takahashi, Koji; Terakado, Masayuki; Ikeda, Ryosuke; Moriyama, Shinichi; Kajiwara, Ken; Sakamoto, Keishi; Hayashi, Kazuo

    2016-03-01

    In Japan Atomic Energy Agency, an ITER relevant control system for ITER gyrotron was developed according to Plant Control Design Handbook. This control system was developed based on ITER CODAC Core System and implemented state machine control of gyrotron operation system, sequential timing control of gyrotron oscillation startup, and data acquisition. The operation of ITER 170 GHz gyrotron was demonstrated with ITER relevant power supply configuration. This system is utilized for gyrotron operation test for ITER procurement. This report describes the architecture of gyrotron local control system, its basic and detailed design, and recent operation results. (author)

  10. Large remote manipulator operating and maintenance experience at IEM cell

    International Nuclear Information System (INIS)

    Hicks, D.F.; McGuinness, P.W.

    1985-01-01

    The Interim Examination and Maintenance (IEM) Cell at the Fast Flux Test Facility (FFTF) has two large Electro-Mechanical Manipulators (EMM's). These manipulators are used for cell operations (processing of reactor core components) as well as general cell maintenance. From our eleven years of operation and maintenance experience with these large EMM's, we have learned many lessons concerning manipulator design. This paper describes the IEM Cell EMM design features and discusses operating and maintenance experience at the IEM Cell

  11. Towards operations on Tore Supra of an ITER relevant inspection robot and associated processes

    International Nuclear Information System (INIS)

    Gargiulo, L.; Cordier, J.J.; Friconneau, J.P.; Grisolia, C.; Palmer, J.D.; Perrot, Y.; Samaille, F.

    2007-01-01

    The aim of the project is to demonstrate on Tore Supra the reliability of a multi-purpose in-vessel remote handling inspection system using a long reach, limited payload carrier. The robot prototype is fully representative of the deployment carrier system that could be required on ITER. The demonstration on Tore Supra will help in the understanding of operation issues that could occur in the tokamak vacuum vessel equipped of actively cooled components. The viewing process that is currently under development will allow close inspection of the Tore Supra plasma facing components that are representative of the ITER divertor targets in terms of confined environment and identification of possible tiles failure of CFC carbon tiles. One of the other potential inspection processes that is foreseen to be tested using the AIA carrier in Tore Supra is the laser ablation system of the CFC armour. It could be fully relevant for the ITER wall detritiation issues. Such process can be simulated on Tore Supra through the deuterium inventory under long-time plasma discharges. The in situ leakage localisation of a damaged plasma facing component is also one of the major ITER maintenance challenges that could use remote handling inspection tools

  12. Towards operations on Tore Supra of an ITER relevant inspection robot and associated processes

    Energy Technology Data Exchange (ETDEWEB)

    Gargiulo, L. [Association Euratom-CEA, DSM/Departement de Recherche sur la Fusion Controlee, CEA/Cadarache, F-13108 Saint Paul Lez Durance Cedex (France)], E-mail: laurent.gargiulo@cea.fr; Cordier, J.J. [Association Euratom-CEA, DSM/Departement de Recherche sur la Fusion Controlee, CEA/Cadarache, F-13108 Saint Paul Lez Durance Cedex (France); Friconneau, J.P. [CEA-LIST Robotics and Interactive Systems Unit, BP6 F-92265 Fontenay aux Roses Cedex (France); Grisolia, C. [Association Euratom-CEA, DSM/Departement de Recherche sur la Fusion Controlee, CEA/Cadarache, F-13108 Saint Paul Lez Durance Cedex (France); Palmer, J.D. [EFDA CSU, Max-Planck-Institut fuer Plasma Physik Boltzmannstr. 2, D-85748 Garching (Germany); Perrot, Y. [CEA-LIST Robotics and Interactive Systems Unit, BP6 F-92265 Fontenay aux Roses Cedex (France); Samaille, F. [Association Euratom-CEA, DSM/Departement de Recherche sur la Fusion Controlee, CEA/Cadarache, F-13108 Saint Paul Lez Durance Cedex (France)

    2007-10-15

    The aim of the project is to demonstrate on Tore Supra the reliability of a multi-purpose in-vessel remote handling inspection system using a long reach, limited payload carrier. The robot prototype is fully representative of the deployment carrier system that could be required on ITER. The demonstration on Tore Supra will help in the understanding of operation issues that could occur in the tokamak vacuum vessel equipped of actively cooled components. The viewing process that is currently under development will allow close inspection of the Tore Supra plasma facing components that are representative of the ITER divertor targets in terms of confined environment and identification of possible tiles failure of CFC carbon tiles. One of the other potential inspection processes that is foreseen to be tested using the AIA carrier in Tore Supra is the laser ablation system of the CFC armour. It could be fully relevant for the ITER wall detritiation issues. Such process can be simulated on Tore Supra through the deuterium inventory under long-time plasma discharges. The in situ leakage localisation of a damaged plasma facing component is also one of the major ITER maintenance challenges that could use remote handling inspection tools.

  13. Operation and maintenance in Genkai PWR Plant

    International Nuclear Information System (INIS)

    Ohta, Shojiro

    1984-01-01

    The No.1 PWR plant with 559 MW capacity in the Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc., required about 115 days for the regular inspection in fiscal 1982 and thereafter, although more maintenance work was done. But No.2 plant of the same type required not more than 80 days. In most cases, the period of one operation cycle was from 10 to 12 months, but in the third operation cycle of No.2 plant, it is expected to be 13 months. The capacity ratio of the whole power station was 75.2% at the end of fiscal 1983. These operational records all exceeded the Japanese average. The plants are two-loop Westinghouse type PWRs, and No.1 plant started the commercial operation of anti h and the increment of P 0 + . (author) apacity ratio of No.1 plant was 71.6%, and that of No.2 plant was 85.5%. The intergranular attack on steam generator tubes was found first in the fifth regular inspection, and also in the sixth and seventh inspections, and the faulty tubes were plugged. The prevention of its spread is the largest problem. The in-service quality assurance activity, the personnel training program and the effort of upgrading the plant availability are reported. (Kako, I.)

  14. Japanese contributions to containment structure, assembly and maintenance and reactor building for ITER

    International Nuclear Information System (INIS)

    Shibanuma, Kiyoshi; Honda, Tsutomu; Kanamori, Naokazu

    1991-06-01

    Joint design work on Conceptual Design Activity of International Thermonuclear Experimental Reactor (ITER) with four parties, Japan, the United States, the Soviet Union and the European Community began in April 1988 and was successfully completed in December 1990. In Japan, the home team was established in wide range of collaboration between JAERI and national institute, universities and heavy industries. The Fusion Experimental Reactor (FER) Team at JAERI is assigned as a core of the Japanese home team to support the joint Team activity and mainly conducted the design and R and D in the area of containment structure, remote handling and plant system. This report mainly describes the Japanese contribution on the ITER containment structure, remote handling and reactor building design. Main areas of contributions are vacuum vessel, attaching locks, electromagnetic analysis, cryostat, port and service line layout for containment structure, in-vessel handling equipment design and analysis, blanket handling equipment design and related short term R and D for assembly and maintenance, and finally reactor building design and analysis based on the equipment and service line layout and components flow during assembly and maintenance. (author)

  15. Life Cycle Costs in Education: Operations & Maintenance Considered.

    Science.gov (United States)

    Moussatche, Helena; Languell-Urquhart, Jennifer; Woodson, Carol

    2000-01-01

    Discusses life cycle cost analysis when deciding on flooring finishes and examines operations and maintenance cost effectiveness relative to hard, resilient, and soft flooring. A chart of evaluated flooring materials' characteristics, appropriate maintenance procedures, and recommended frequency is included. (GR)

  16. On Controlled Iterated GSM Mappings and Related Operations

    NARCIS (Netherlands)

    Asveld, P.R.J.

    1979-01-01

    In [17] G. Paun studied families of languages generated by iterated gsm mappings, iterated finite substitutions, and iterated homomorphisms. In this note we generalize some results in [17], and we discuss the relation between iterated finite substitutions (homomorphisms) and (deterministic) tabled

  17. On Controlled Iterated GSM Mappings and Related Operations

    NARCIS (Netherlands)

    Asveld, P.R.J.

    1980-01-01

    In [17] G. Paun studied families of languages generated by iterated gsm mappings, iterated finite substitutions, and iterated homomorphisms. In this note we generalize some results in [17], and we discuss the relation between iterated finite substitutions (homomorphisms) and (deterministic) tabled

  18. TRUPACT-II Operating and Maintenance Instructions

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse Electric Corporation, Waste Isolation Division

    1999-12-31

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II) Shipping Package and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP) and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9218. In the event there is a conflict between this document and the TRUPACT-II SARP, the TRUPACT-II SARP shall govern. TRUPACT-II C of C number 9218 states, ''... each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' It further states, ''... each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the application.'' Chapter 9 of the TRUPACT-II SARP charges the Westinghouse Electric Corporation Waste Isolation Division (WID) with assuring that the TRUPACT-II is used in accordance with the requirements of the C of C. To meet this requirement and verify consistency of operations when loading and unloading the TRUPACT-II on the trailer, placing a payload in the packaging, unloading the payload from the packaging, or performing maintenance, the U.S. Department of Energy Carlsbad Area Office (U.S. DOE/CAO) finds it necessary to implement the changes that follow. This TRUPACT-II maintenance document represents a change to previous philosophy regarding site specific procedures for the use of the TRUPACT-II. This document details the instructions to be followed to consistently operate and maintain the TRUPACT-II. The intent of these instructions is to ensure that all users of the TRUPACT-II follow the same or equivalent instructions. Users may achieve this intent by any of the following methods: (1

  19. Design of the ITER magnets to provide plasma operational flexibility

    International Nuclear Information System (INIS)

    Mitchell, N.; Bessette, D.; Ferrari, M.; Huguet, M.; Jong, C.; Takahashi, Y.; Yoshida, K.; Maix, R.; Krivchenkov, Y.; Zapretilina, E.

    2005-01-01

    The ITER magnets have been optimised and refined since the ITER Final Design Report (FDR) in 2001. Multiple design options have been eliminated and there is improved ability to drive a wide range of plasma configurations. Design iterations on the TF out of plane supports have eliminated stress concentrations in the inner keyways and have led to the choice of a so called friction-joint on the outside. The closure procedure for the TF case has been changed, with a new case segmentation, less risk of winding pack damage from shrinkage and better filling of the case-winding gaps. Selection of compact joints for the CS has enabled the peak field and cyclic stress levels in the conductor to be reduced while maintaining the flux capability. The uncertainty in the nuclear heat levels in the inner legs of the TF coils, and the need to operate with plasma nuclear powers from 360 to 700MW, lead to a thermal screen on the inside of the case with variable cooling capability. The electrical insulation specification has been refined after irradiation test results to give a better margin on the onset of degradation after operation to 3MWa/m 2 . The RWM stabilisation provided by the side CC has been extended by accepting higher voltages and heating from AC losses. R and D results from the model coil tests have shown lower than expected design margins for the Nb3Sn conductors. This has been offset by adopting the latest advances in strand performance, and the margins of the new conductor will be confirmed by testing in 2005. Preparation for procurement is underway with considerations on technically acceptable ways of splitting the magnet supply. (author)

  20. Development of radiation-hard electric connector with ball bearing for in-vessel remote maintenance equipment of ITER

    International Nuclear Information System (INIS)

    Ito, Akira; Obara, Kenjiro; Tada, Eisuke; Morita, Yousuke; Yagi, Toshiaki; Iida, Kazuhisa; Sato, Masaru.

    1997-12-01

    Development of radiation-hard electric connector with ball bearing for in-vessel remote maintenance equipment of ITER (International Thermonuclear Experimental Reactor) has been conducted. Since the in-vessel remote maintenance equipment is operated under the condition of 10 6 R/h gamma ray dose rate, the electric connector has to be radiation hard for an accumulation dose of 10 10 R. In addition, the simple attachment/removal mechanism is essential for remote operation. For this, the alumina (Al203) ceramics and a ball bearing were adopted to electric insulator and plug (male) of connector, respectively. The handling tests on attachment/removal of the connector were conducted by using master slave manipulator and general purpose robot with handling tool, and as a result, the validity of the attachment/removal mechanism was verified. In the gamma ray irradiation tests, which are under way, no degradation in break down voltage (1000V 1min.) up to 10 10 R was confirmed. However insulation resistance and contact resistance between contact pin and contact socket were deteriorated in proportion to the accumulation dose. Increase of contact resistance is considered due to an erosion of contact pin. (author)

  1. Water hydraulic manipulator for fail safe and fault tolerant remote handling operations at ITER

    International Nuclear Information System (INIS)

    Nieminen, Peetu; Esque, Salvador; Muhammad, Ali; Mattila, Jouni; Vaeyrynen, Jukka; Siuko, Mikko; Vilenius, Matti

    2009-01-01

    Department of Intelligent Hydraulics and Automation (IHA) of Tampere University of Technology has been involved in the European Fusion program since 1994 within the ITER reactor maintenance activities. In this paper we discuss the design and development of a six degrees of freedom water hydraulic manipulator with a force feedback for teleoperation tasks. The manipulator is planned to be delivered to Divertor Test Platform 2 (DTP2) during year 2008. The paper also discusses the possibility to improve the fail safe and redundant operation of the manipulator. During the design of the water hydraulic manipulator, special provisions have been made in order to meet the safety requirements such as servo valve block for redundant operation and safety vane brakes for fail safe operation.

  2. Iter

    Science.gov (United States)

    Iotti, Robert

    2015-04-01

    ITER is an international experimental facility being built by seven Parties to demonstrate the long term potential of fusion energy. The ITER Joint Implementation Agreement (JIA) defines the structure and governance model of such cooperation. There are a number of necessary conditions for such international projects to be successful: a complete design, strong systems engineering working with an agreed set of requirements, an experienced organization with systems and plans in place to manage the project, a cost estimate backed by industry, and someone in charge. Unfortunately for ITER many of these conditions were not present. The paper discusses the priorities in the JIA which led to setting up the project with a Central Integrating Organization (IO) in Cadarache, France as the ITER HQ, and seven Domestic Agencies (DAs) located in the countries of the Parties, responsible for delivering 90%+ of the project hardware as Contributions-in-Kind and also financial contributions to the IO, as ``Contributions-in-Cash.'' Theoretically the Director General (DG) is responsible for everything. In practice the DG does not have the power to control the work of the DAs, and there is not an effective management structure enabling the IO and the DAs to arbitrate disputes, so the project is not really managed, but is a loose collaboration of competing interests. Any DA can effectively block a decision reached by the DG. Inefficiencies in completing design while setting up a competent organization from scratch contributed to the delays and cost increases during the initial few years. So did the fact that the original estimate was not developed from industry input. Unforeseen inflation and market demand on certain commodities/materials further exacerbated the cost increases. Since then, improvements are debatable. Does this mean that the governance model of ITER is a wrong model for international scientific cooperation? I do not believe so. Had the necessary conditions for success

  3. Towards operations on Tore Supra of an ITER relevant inspection robot and associated processes

    International Nuclear Information System (INIS)

    Laurent Gargiulo, L.; Cordier, J.-J.; Samaille, F.; Grisolia, Ch.; Perrot, Y.; Olivier, D.; Friconneau, J.-P.; Palmer, J.

    2006-01-01

    The aim of the project is to demonstrate on Tore Supra the reliability of a multi-purpose in-vessel Remote Handling inspection system using a long reach, limited payload carrier. This project called AIA (Articulated Inspection Arm) is currently being developed at CEA under a European EFDA work program. The paper describes the detailed design, the manufacturing processes and the results of the first module test campaign in the CEA Tore Supra ME60 facility, at representative vacuum, temperature and nominal loading conditions. The second part of this work that is reported in the paper, concerns the description of the whole integration of the device on the Tore Supra tokamak that is foreseen to be operated on Tore Supra early 2007. The deployer system and the 10 m long storage vacuum vessel are presented. The robot prototype is fully representative of the deployment carrier system that could be required on ITER. The demonstration on Tore Supra will help in the understanding of operation issues that could occur in the tokamak vacuum vessel equipped of actively cooled components. The viewing process that is currently under development is presented in the paper. It will allow close inspection of the Tore Supra Plasma Facing Components that are representative of the ITER divertor targets in terms of confined environment and identification of possible tiles failure of CFC carbon tiles. Such viewing process could be used on ITER during the early stage of operation under a limited radiation level. The AIA technology is also showing promising potential for generic application in alternative systems for ITER. The feasibility study for viewing inspection of the beam line components in the neutral beam test facility is presented. One of the other potential inspection processes that is foreseen to be tested using the AIA carrier in Tore Supra is the laser ablation system of the CFC armour. It could be fully relevant for the ITER wall detritiation issues. Such process can be

  4. An Automated Baseline Correction Method Based on Iterative Morphological Operations.

    Science.gov (United States)

    Chen, Yunliang; Dai, Liankui

    2018-05-01

    Raman spectra usually suffer from baseline drift caused by fluorescence or other reasons. Therefore, baseline correction is a necessary and crucial step that must be performed before subsequent processing and analysis of Raman spectra. An automated baseline correction method based on iterative morphological operations is proposed in this work. The method can adaptively determine the structuring element first and then gradually remove the spectral peaks during iteration to get an estimated baseline. Experiments on simulated data and real-world Raman data show that the proposed method is accurate, fast, and flexible for handling different kinds of baselines in various practical situations. The comparison of the proposed method with some state-of-the-art baseline correction methods demonstrates its advantages over the existing methods in terms of accuracy, adaptability, and flexibility. Although only Raman spectra are investigated in this paper, the proposed method is hopefully to be used for the baseline correction of other analytical instrumental signals, such as IR spectra and chromatograms.

  5. Operations and Maintenance Cost for Stratified Buildings: A Critical Review

    Directory of Open Access Journals (Sweden)

    Che-Ghani Nor Zaimah

    2016-01-01

    Full Text Available Building maintenance is essential in preserving buildings’ appearance and performance. It needs to upkeep the building performance to prolong its value and building life cycle. Malaysia is still lacking in managing cost for building operation and maintenance. It has been found that the cost for housing maintenance is high due to poor maintenance practices. In order to get better understanding on how to manage the cost, this study reviews the contributing factors that affecting operation and maintenance cost of stratified buildings in Malaysia. The research first identified the factors through extensive literature review and scrutinize on factors that affecting and can minimize operation and maintenance cost. This literature review offers insight into building maintenance scenario in Malaysia focusing on the issues and challenges. The study also finds that operation and maintenance cost for housing in Malaysia is still in poor state. Interestingly, this paper revealed that operation and maintenance cost is also influenced by three significant factors like expectation of tenants, building characteristics and building defects. Measures to reduce the housing operation and maintenance cost are also highlighted so that this study can be a stepping stone towards proposing efficient and effective facilities management strategies for affordable housing in future.

  6. ITER operational space for full plasma current H-mode operation

    Energy Technology Data Exchange (ETDEWEB)

    Mattei, M. [Assoc. Euratom-ENEA-CREATE, Seconda University di Napoli, Aversa (Italy)], E-mail: massimiliano.mattei@unirc.it; Cavinato, M.; Saibene, G.; Portone, A. [Fusion for Energy Joint Undertaking, 08019 Barcelona (Spain); Albanese, R.; Ambrosino, G. [Assoc. Euratom-ENEA-CREATE, University Napoli Federico II, Napoli (Italy); Horton, L.D. [Max Planck-Institut fur Plasmaphysik, EURATOM-Association, Garching (Germany); Kessel, C. [Princeton Plasma Physics Laboratory, Princeton University (United States); Koechl, F. [Assoc. EURATOM-OAW/ATI, Vienna (Austria); Lomas, P.J. [Euratom/UKAEA Fusion Assoc., Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Nunes, I. [Assoc. EURATOM/IST, Centro de Fusao Nuclear, Lisbon (Portugal); Parail, V. [Max Planck-Institut fur Plasmaphysik, EURATOM-Association, Garching (Germany); Sartori, R. [Fusion for Energy Joint Undertaking, 08019 Barcelona (Spain); Sips, A.C.C. [Max Planck-Institut fur Plasmaphysik, EURATOM-Association, Garching (Germany); Thomas, P.R. [Fusion for Energy Joint Undertaking, 08019 Barcelona (Spain)

    2009-06-15

    Sensitivity studies performed as part of the ITER IO design review highlighted a very stiff dependence of the maximum Q attainable on the machine parameters. In particular, in the considered range, the achievable Q scales with I{sub p}{sup 4}. As a consequence, the achievement of the ITER objective of Q = 10 requires the machine to be routinely operated at a nominal current I{sub p} of 15 MA, and at full toroidal field BT of 5.3 T. This paper analyses the capabilities of the poloidal field (PF) system (including the central solenoid) of ITER against realistic full current plasma scenarios. An exploration of the ITER operational space for the 15 and 17 MA inductive scenario is carried out. An extensive analysis includes the evaluation of margins for the closed loop shape control action. The overall results of this analysis indicate that the control of a 15 MA plasma in ITER is likely to be adequate in the range of li 0.7-0.9 whereas, for a 17 MA plasma, control capabilities are strongly reduced. The ITER operational space, provided by the reference pre-2008 PF system, was rather limited if compared to the range of parameters normally observed in present experiment. Proposals for increasing the current and field limits on PF2, PF5 and PF6, adjustment on the number of turns in some of the PF coils, changes to the divertor dome geometry, to the conductor of PF6 to Nb3Sn, moving PF6 radially and/or vertically are described and evaluated in the paper. Some of them have been included in 2008 ITER revised configuration.

  7. An iterative approach for the optimization of pavement maintenance management at the network level.

    Science.gov (United States)

    Torres-Machí, Cristina; Chamorro, Alondra; Videla, Carlos; Pellicer, Eugenio; Yepes, Víctor

    2014-01-01

    Pavement maintenance is one of the major issues of public agencies. Insufficient investment or inefficient maintenance strategies lead to high economic expenses in the long term. Under budgetary restrictions, the optimal allocation of resources becomes a crucial aspect. Two traditional approaches (sequential and holistic) and four classes of optimization methods (selection based on ranking, mathematical optimization, near optimization, and other methods) have been applied to solve this problem. They vary in the number of alternatives considered and how the selection process is performed. Therefore, a previous understanding of the problem is mandatory to identify the most suitable approach and method for a particular network. This study aims to assist highway agencies, researchers, and practitioners on when and how to apply available methods based on a comparative analysis of the current state of the practice. Holistic approach tackles the problem considering the overall network condition, while the sequential approach is easier to implement and understand, but may lead to solutions far from optimal. Scenarios defining the suitability of these approaches are defined. Finally, an iterative approach gathering the advantages of traditional approaches is proposed and applied in a case study. The proposed approach considers the overall network condition in a simpler and more intuitive manner than the holistic approach.

  8. An Iterative Approach for the Optimization of Pavement Maintenance Management at the Network Level

    Directory of Open Access Journals (Sweden)

    Cristina Torres-Machí

    2014-01-01

    Full Text Available Pavement maintenance is one of the major issues of public agencies. Insufficient investment or inefficient maintenance strategies lead to high economic expenses in the long term. Under budgetary restrictions, the optimal allocation of resources becomes a crucial aspect. Two traditional approaches (sequential and holistic and four classes of optimization methods (selection based on ranking, mathematical optimization, near optimization, and other methods have been applied to solve this problem. They vary in the number of alternatives considered and how the selection process is performed. Therefore, a previous understanding of the problem is mandatory to identify the most suitable approach and method for a particular network. This study aims to assist highway agencies, researchers, and practitioners on when and how to apply available methods based on a comparative analysis of the current state of the practice. Holistic approach tackles the problem considering the overall network condition, while the sequential approach is easier to implement and understand, but may lead to solutions far from optimal. Scenarios defining the suitability of these approaches are defined. Finally, an iterative approach gathering the advantages of traditional approaches is proposed and applied in a case study. The proposed approach considers the overall network condition in a simpler and more intuitive manner than the holistic approach.

  9. Technical information report: Plasma melter operation, reliability, and maintenance analysis

    International Nuclear Information System (INIS)

    Hendrickson, D.W.

    1995-01-01

    This document provides a technical report of operability, reliability, and maintenance of a plasma melter for low-level waste vitrification, in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. A process description is provided that minimizes maintenance and downtime and includes material and energy balances, equipment sizes and arrangement, startup/operation/maintence/shutdown cycle descriptions, and basis for scale-up to a 200 metric ton/day production facility. Operational requirements are provided including utilities, feeds, labor, and maintenance. Equipment reliability estimates and maintenance requirements are provided which includes a list of failure modes, responses, and consequences

  10. The ITER EC H&CD Upper Launcher: Analysis of vertical Remote Handling applied to the BSM maintenance

    NARCIS (Netherlands)

    Grossetti, G.; Aiello, G.; Heemskerk, C.; Elzendoorn, B.; Geßner, R.; Koning, J.; Meier, A.; Ronden, D.; Späh, P.; Scherer, T.; Schreck, S.; Strauß, D.; Vaccaro, A.

    2013-01-01

    This paper deals with Remote Handling activities foreseen on the Blanket Shield Module, the plasma facing component of the ITER Electron Cyclotron Heating and Current Drive Upper Launcher. The maintenance configuration considered here is the Vertical Remote Handling, meaning gravity acting along the

  11. 24 CFR 1006.325 - Maintenance, management and efficient operation.

    Science.gov (United States)

    2010-04-01

    ... § 1006.325 Maintenance, management and efficient operation. (a) Written policies. The DHHL must develop... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Maintenance, management and efficient operation. 1006.325 Section 1006.325 Housing and Urban Development Regulations Relating to Housing...

  12. 7 CFR 654.12 - Financing operations and maintenance.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Financing operations and maintenance. 654.12 Section 654.12 Agriculture Regulations of the Department of Agriculture (Continued) NATURAL RESOURCES... Financially-Assisted Projects § 654.12 Financing operations and maintenance. Sources of funds needed to...

  13. 38th Annual Maintenance & Operations Cost Study for Colleges

    Science.gov (United States)

    Agron, Joe

    2009-01-01

    The nation's colleges are feeling the pinch of the economic downturn, and maintenance and operations (M&O) budgets especially are under pressure. This article presents data from the 38th annual Maintenance & Operations Cost Study for colleges that can help one in benchmarking expenditures at one's institution. Data provided only targets two-year…

  14. Risk-Based Operation and Maintenance of Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Nielsen, Jannie Jessen; Sørensen, John Dalsgaard

    2009-01-01

    For offshore wind turbines costs to operation and maintenance are substantial. This paper describes a risk-based lifecycle approach for optimal planning of operation and maintenance. The approach is based on pre-posterior Bayesian decision theory. Deterioration mechanisms such as fatigue, corrosion...

  15. 38th Annual Maintenance & Operations Cost Study for Schools

    Science.gov (United States)

    Agron, Joe

    2009-01-01

    Despite the worst economic environment in generations, spending by K-12 institutions on maintenance and operations (M&O) held its own--defying historical trends that have shown M&O spending among the most affected in times of budget tightening. This article presents data from the 38th annual Maintenance & Operations Cost Study for…

  16. Gas characterization system operation, maintenance, and calibration plan

    International Nuclear Information System (INIS)

    Tate, D.D.

    1996-01-01

    This document details the responsibilities and requirements for operation, maintenance, and calibration of the Gas Characterization Systems (GCS) analytical instrumentation. It further, defines the division of responsibility between the Characterization Monitoring Development organization and Tank Farms Operations

  17. Multi-canister overpack operations and maintenance manual

    International Nuclear Information System (INIS)

    PIERCE, S.R.

    1999-01-01

    This manual provides general operating and maintenance instructions for the Multi-Canister Overpack. Procedure outlines included are conceptual in nature and will be modified, expanded, and refined during preparation of detailed operating procedures

  18. Risk mitigation strategies for operations and maintenance activities.

    Science.gov (United States)

    2012-04-01

    The objective of this research was to investigate the application of integrated risk modeling to operations and maintenance activities, specifically moving operations, such as pavement testing, pavement marking, painting, snow removal, shoulder work,...

  19. Intelligent controller of a flexible hybrid robot machine for ITER assembly and maintenance

    International Nuclear Information System (INIS)

    Al-saedi, Mazin I.; Wu, Huapeng; Handroos, Heikki

    2014-01-01

    Highlights: • Studying flexible multibody dynamic of hybrid parallel robot. • Investigating fuzzy-PD controller to control a hybrid flexible hydraulically driven robot. • Investigating ANFIS-PD controller to control a hybrid flexible robot. Compare to traditional PID this method gives better performance. • Using the equilibrium of reaction forces between the parallel and serial parts of hybrid robot to control the serial part hydraulically driven. - Abstract: The assembly and maintenance of International Thermonuclear Experimental Reactor (ITER) vacuum vessel (VV) is highly challenging since the tasks performed by the robot involve welding, material handling, and machine cutting from inside the VV. To fulfill the tasks in ITER application, this paper presents a hybrid redundant manipulator with four DOFs provided by serial kinematic axes and six DOFs by parallel mechanism. Thus, in machining, to achieve greater end-effector trajectory tracking accuracy for surface quality, a robust control of the actuators for the flexible link has to be deduced. In this paper, the intelligent control of a hydraulically driven parallel robot part based on the dynamic model and two control schemes have been investigated: (1) fuzzy-PID self tuning controller composed of the conventional PID control and with fuzzy logic; (2) adaptive neuro-fuzzy inference system-PID (ANFIS-PID) self tuning of the gains of the PID controller, which are implemented independently to control each hydraulic cylinder of the parallel robot based on rod position predictions. The obtained results of the fuzzy-PID and ANFIS-PID self tuning controller can reduce more tracking errors than the conventional PID controller. Subsequently, the serial component of the hybrid robot can be analyzed using the equilibrium of reaction forces at the universal joint connections of the hexa-element. To achieve precise positional control of the end effector for maximum precision machining, the hydraulic cylinder should

  20. Intelligent controller of a flexible hybrid robot machine for ITER assembly and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Al-saedi, Mazin I., E-mail: mazin.al-saedi@lut.fi; Wu, Huapeng; Handroos, Heikki

    2014-10-15

    Highlights: • Studying flexible multibody dynamic of hybrid parallel robot. • Investigating fuzzy-PD controller to control a hybrid flexible hydraulically driven robot. • Investigating ANFIS-PD controller to control a hybrid flexible robot. Compare to traditional PID this method gives better performance. • Using the equilibrium of reaction forces between the parallel and serial parts of hybrid robot to control the serial part hydraulically driven. - Abstract: The assembly and maintenance of International Thermonuclear Experimental Reactor (ITER) vacuum vessel (VV) is highly challenging since the tasks performed by the robot involve welding, material handling, and machine cutting from inside the VV. To fulfill the tasks in ITER application, this paper presents a hybrid redundant manipulator with four DOFs provided by serial kinematic axes and six DOFs by parallel mechanism. Thus, in machining, to achieve greater end-effector trajectory tracking accuracy for surface quality, a robust control of the actuators for the flexible link has to be deduced. In this paper, the intelligent control of a hydraulically driven parallel robot part based on the dynamic model and two control schemes have been investigated: (1) fuzzy-PID self tuning controller composed of the conventional PID control and with fuzzy logic; (2) adaptive neuro-fuzzy inference system-PID (ANFIS-PID) self tuning of the gains of the PID controller, which are implemented independently to control each hydraulic cylinder of the parallel robot based on rod position predictions. The obtained results of the fuzzy-PID and ANFIS-PID self tuning controller can reduce more tracking errors than the conventional PID controller. Subsequently, the serial component of the hybrid robot can be analyzed using the equilibrium of reaction forces at the universal joint connections of the hexa-element. To achieve precise positional control of the end effector for maximum precision machining, the hydraulic cylinder should

  1. Status of reliability in determining SDDR for manual maintenance activities in ITER: Quality assessment of relevant activation cross sections involved

    International Nuclear Information System (INIS)

    Garcia, R.; Garcia, M.; Pampin, R.; Sanz, J.

    2016-01-01

    Highlights: • Feasibility of manual maintenance activities in ITER port cell and port interspace. • Activation of relevant materials and components placed in the current ITER model. • Dominant radionuclides and pathways for shutdown dose rate in ITER. • Quality analysis of typically used EAF and TENDL activation libraries is performed. • EAF performance found as trustworthy with slight recommended improvements. - Abstract: This paper assesses the quality of the EAF-2007 and 2010 activation cross sections for relevant reactions in the determination of the Shutdown Dose Rate (SDDR) in the Port Cell (PC) and Port Interspace (PI) areas of ITER. For each of relevant ITER materials, dominant radionuclides responsible of SDDR and their production pathways are listed. This information comes from a review of the recent reports/papers about SDDR in ITER and own calculations. A total of 26 relevant pathways are found. The quality of these cross sections pathways is assessed following EAF validation procedure, and for those found as not validated last TENDL library versions have been investigated in order to check possible improvements when compared to EAF. The use of EAF libraries is found as trustworthy and it is recommended for the prediction of SDDR in the ITER PC and PI. However, 3 cross section reactions are considered for further improvement: Co59(n,2n)Co58, Cu63(n,g)Cu64 and Cr50(n,g)Cr51.

  2. Status of reliability in determining SDDR for manual maintenance activities in ITER: Quality assessment of relevant activation cross sections involved

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, R., E-mail: rgarciam@ind.uned.es [UNED, Power Engineering Department, C/Juan del Rosal 12, 28040 Madrid (Spain); Garcia, M. [UNED, Power Engineering Department, C/Juan del Rosal 12, 28040 Madrid (Spain); Pampin, R. [F4E, Torres Diagonal Litoral B3, Barcelona (Spain); Sanz, J. [UNED, Power Engineering Department, C/Juan del Rosal 12, 28040 Madrid (Spain)

    2016-11-15

    Highlights: • Feasibility of manual maintenance activities in ITER port cell and port interspace. • Activation of relevant materials and components placed in the current ITER model. • Dominant radionuclides and pathways for shutdown dose rate in ITER. • Quality analysis of typically used EAF and TENDL activation libraries is performed. • EAF performance found as trustworthy with slight recommended improvements. - Abstract: This paper assesses the quality of the EAF-2007 and 2010 activation cross sections for relevant reactions in the determination of the Shutdown Dose Rate (SDDR) in the Port Cell (PC) and Port Interspace (PI) areas of ITER. For each of relevant ITER materials, dominant radionuclides responsible of SDDR and their production pathways are listed. This information comes from a review of the recent reports/papers about SDDR in ITER and own calculations. A total of 26 relevant pathways are found. The quality of these cross sections pathways is assessed following EAF validation procedure, and for those found as not validated last TENDL library versions have been investigated in order to check possible improvements when compared to EAF. The use of EAF libraries is found as trustworthy and it is recommended for the prediction of SDDR in the ITER PC and PI. However, 3 cross section reactions are considered for further improvement: Co59(n,2n)Co58, Cu63(n,g)Cu64 and Cr50(n,g)Cr51.

  3. Nonlinear Burn Control and Operating Point Optimization in ITER

    Science.gov (United States)

    Boyer, Mark; Schuster, Eugenio

    2013-10-01

    Control of the fusion power through regulation of the plasma density and temperature will be essential for achieving and maintaining desired operating points in fusion reactors and burning plasma experiments like ITER. In this work, a volume averaged model for the evolution of the density of energy, deuterium and tritium fuel ions, alpha-particles, and impurity ions is used to synthesize a multi-input multi-output nonlinear feedback controller for stabilizing and modulating the burn condition. Adaptive control techniques are used to account for uncertainty in model parameters, including particle confinement times and recycling rates. The control approach makes use of the different possible methods for altering the fusion power, including adjusting the temperature through auxiliary heating, modulating the density and isotopic mix through fueling, and altering the impurity density through impurity injection. Furthermore, a model-based optimization scheme is proposed to drive the system as close as possible to desired fusion power and temperature references. Constraints are considered in the optimization scheme to ensure that, for example, density and beta limits are avoided, and that optimal operation is achieved even when actuators reach saturation. Supported by the NSF CAREER award program (ECCS-0645086).

  4. PROCESS OF CHANGES OF MAINTENANCE-FREE ONBOARD SYSTEM OPERATIONAL STATUS BETWEEN SCHEDULED MAINTENANCES

    Directory of Open Access Journals (Sweden)

    Andrey Mikhaylovich Bronnikov

    2017-01-01

    Full Text Available In this article the authors consider the problem of simulating the process of a maintenance-free between scheduled maintenance aircraft system operational status changes, which failure during the flight leads to the disaster. On-board equipment with automatic self-repair between routine maintenance in the event the components fail is called maintenance-free. During operation, onboard equipment accumulates failures maintaining its functions with a safety level not lower than the required minimum. Trouble shooting is carried out either at the end of between-maintenance period (as a rule, or after the failure, which led to the functions disorder or to the decrease below the target level of flight safety (as an exception. The system contains both redundant and nonredundant units and elements with the known failure rates. The system can be in one of the three states: operable, extreme, failed. The excessive redundant elements allow the system to accumulate failures which are repaired during the routine maintenance. The process of system operational status changes is described with the discrete-continuous model in the flight time. Basing on the information about the probabilities of the on-board equipment being in an operable, extreme or failed state, it is possible to calculate such complex efficiency indicators as the average loss of sorties, the average operating costs, the expected number of emergency recovery operations and others. Numerical studies have been conducted to validate the proposed model. It is believed that maintenance work completely updates the system. The analysis of these indicators will allow to evaluate the maintenance-free aircraft equipment operation efficiency, as well as to make an effectiveness comparison with other methods of technical operation. The model can be also used to assess the technical operation systems performance. The model can be used to optimize the period between maintenance.

  5. Operation of an ITER relevant inspection robot on Tore Supra tokamak

    Energy Technology Data Exchange (ETDEWEB)

    Gargiulo, Laurent [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France)], E-mail: laurent.gargiulo@cea.fr; Bayetti, Pascal; Bruno, Vincent; Hatchressian, Jean-Claude; Hernandez, Caroline; Houry, Michael [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Keller, Delphine [CEA, LIST, Service de Robotique Interactive, F-92265 Fontenay aux Roses (France); Martins, Jean-Pierre [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Measson, Yvan; Perrot, Yann [CEA, LIST, Service de Robotique Interactive, F-92265 Fontenay aux Roses (France); Samaille, Frank [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France)

    2009-06-15

    Robotic operations are one of the major maintenance challenges for ITER and future fusion reactors. CEA has developed a multipurpose carrier able to realize deployments in the plasma vessel without breaking the Ultra High Vacuum (UHV) and temperature conditioning. A 6 years R and D programme was jointly conducted by CEA-LIST Interactive Robotics Unit and the Institute for Magnetic Fusion Research (IRFM) in order to demonstrate the feasibility and reliability of an in-vessel inspection robot relevant to ITER requirements. The Articulated Inspection Arm robot (AIA) is an 8-m long multilink carrier with a payload up to 10 kg operable between plasma under tokamak conditioning environment; its geometry allows a complete close inspection of Plasma Facing Components (PFCs) of the Tore Supra vessel. Different tools are being developed by CEA to be plugged at the front head of the carrier. The diagnostic presently in operation consists in a viewing system offering accurate visual inspection of PFCs. Leak detection of first wall based on helium sniffing and laser compact system for carbon co-deposited layers characterizations or treatments are also considered for demonstration. In April 2008, the AIA robot equipped with its vision diagnostic has realized a complete deployment into Tore Supra and the first closed inspection of the vessel under UHV conditions. During the upcoming experimental campaign, the same operation will be performed under relevant conditions (10{sup -6} Pa and 120 deg. C) after a conditioning phase at 200 deg. C to avoid outgassing pollution of the chamber. This paper describes the different steps of the project development, robot capabilities with the present operations conducted on Tore Supra and future requirements for making the robot a tool for tokamak routine operation.

  6. Surface Moisture Measurement System Operation and Maintenance Manual

    International Nuclear Information System (INIS)

    Ritter, G.A.; Pearce, K.L.; Stokes, T.L.

    1995-12-01

    This operations and maintenance manual addresses deployment, equipment and field hazards, operating instructions, calibration verification, removal, maintenance, and other pertinent information necessary to safely operate and store the Surface Moisture Measurement System (SMMS) and Liquid Observation Well Moisture Measurement System (LOWMMS). These systems were developed primarily in support of Tank Waste Remediation System (TWRS) Safety Programs for moisture measurement in organic and ferrocyanide watch list tanks

  7. RA reactor operation and maintenance in 1992, Part 1

    International Nuclear Information System (INIS)

    Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Majstorovic, D.; Tanaskovic, M.

    1992-01-01

    During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems [sr

  8. Kinematic analysis on rail development into vacuum vessel for ITER blanket maintenance

    International Nuclear Information System (INIS)

    Kakudate, Satoshi; Shibanuma, Kiyoshi

    2006-01-01

    The vehicle manipulator system for blanket maintenance is used as a main driving mechanism for rail development, and three driving mechanisms d1, d2 (or d2') and d3 are used as cycle sequence of the repeated operations for rail development. This repeated operation can develop the articulated rail into the vacuum vessel. The rail development scenario, kinematic analysis model for rail development without any driving mechanisms in the rail joints, equations defined the angular between two rail links, identification of rail link at repeated operation, numerical analysis results on rail deployment under the forced position control of l i+1 , new rail development scenario using two driving mechanisms d1 and d2''under one cycle sequence of the repeated operations, and rail development test are reported. (S.Y.)

  9. Transport package maintenance requirements and operations

    International Nuclear Information System (INIS)

    Tyacke, M.J.; Ball, L.J.; Ayers, A.L. Jr.; Hayes, G.R.; Anselmo, A.A.

    1988-01-01

    The NuPac 125-B rail cask, which transports the damaged core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL), is the only new spent-fuel rail shipping cask to be licensed in the United States within the last decade. EG ampersand G Idaho, Inc. (EG ampersand G), acting on behalf of the US Department of Energy, is responsible for ensuring that those new casks and rail cars are properly maintained per regulatory requirements. Both the casks and rail cars have comprehensive in-service inspection and preventive maintenance programs, which are more involved than implied by the requirements. The TMI-2 shipping campaign is the most ambitious spent-fuel transport activity being conducted in the nuclear industry. The experience gained in this campaign, as it relates to maintenance of a transport system, should be of interest and have direct applicability to similar shipping activities planned in the years ahead

  10. Operation and maintenance strategies for wave energy converters

    DEFF Research Database (Denmark)

    Ambühl, Simon; Marquis, Laurent; Kofoed, Jens Peter

    2015-01-01

    costs including costs due to lost electricity production are minimized. The risk-based approach is compared with an approach where only boats are used and another approach where the target is to minimize the downtime of the device. This article presents a dynamic approach for total operation......Inspection and maintenance costs are a significant contributor to the cost of energy for wave energy converters. There are different operation and maintenance strategies for wave energy converters. Maintenance can be performed after failure (corrective) or before a breakdown (preventive) occurs....... Furthermore, a helicopter and boats can be used to transport equipment and personnel to the device, or the whole device can be towed to a harbour for operation and maintenance actions. This article describes, among others, a risk-based inspection and maintenance planning approach where the overall repair...

  11. Knowledge representation for integrated plant operation and maintenance

    DEFF Research Database (Denmark)

    Lind, Morten

    2010-01-01

    Integrated operation and maintenance of process plants has many advantages. One advantage is the improved economy obtained by reducing the number of plant shutdowns. Another is to increase reliability of operation by monitoring of risk levels during on-line maintenance. Integrated plant operation...... and maintenance require knowledge bases which can capture the interactions between the two plant activities. As an example, taking out a component or a subsystem for maintenance during operation will require a knowledge base representing the interactions between plant structure, functions, operating states...... and goals and incorporate knowledge about redundancy and reliability data. Multilevel Flow Modeling can be used build knowledge bases representing plant goals and functions and has been applied for fault diagnosis and supervisory control but currently it does not take into account structural information...

  12. 7 CFR 1767.27 - Operation and maintenance expenses.

    Science.gov (United States)

    2010-01-01

    ..., DEPARTMENT OF AGRICULTURE (CONTINUED) ACCOUNTING REQUIREMENTS FOR RUS ELECTRIC BORROWERS Uniform System of... Waterways 544Maintenance of Electric Plant 545Maintenance of Miscellaneous Hydraulic Plant Other Power....1Load Dispatch-Reliability 561.2Load Dispatch-Monitor and Operate Transmission System 561.3Load Dispatch...

  13. 49 CFR 236.919 - Operations and Maintenance Manual.

    Science.gov (United States)

    2010-10-01

    ..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Standards for Processor-Based Signal and Train Control Systems § 236.919 Operations and Maintenance Manual. (a... identify all software versions, revisions, and revision dates. Plans must be legible and correct. (c...

  14. 49 CFR 236.1039 - Operations and Maintenance Manual.

    Science.gov (United States)

    2010-10-01

    ..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Positive Train Control Systems § 236.1039 Operations and Maintenance Manual. (a) The railroad shall catalog and... software versions, revisions, and revision dates. Plans must be legible and correct. (c) Hardware, software...

  15. 14 CFR 171.273 - Maintenance and operations requirements.

    Science.gov (United States)

    2010-01-01

    ... authorized persons. (3) FCC licensing requirements for operations and maintenance personnel. (4) Posting of..., with a maximum corrective maintenance time of not greater than 1.5 hours. This measure applies to... than 1,500 hours. This measure applies to unscheduled outages, out-of-tolerance conditions, and...

  16. Remote maintenance of an operational fusion experiment

    Energy Technology Data Exchange (ETDEWEB)

    Kiptily, V.G.; Jarvis, O.N.; Popovichev, S. [Euratom/UKAEA Fusion Assoc., Culham Science Centre, Abingdon, Oxon. (United Kingdom)] [and others

    2001-07-01

    Optimisation of auxiliary plasma heating by means of Ion Cyclotron Radio-Frequency (ICRF) and Neutral Beam Injection (NBI) as envisaged for the future fusion reactors is one of the main priorities in present research at today's tokamaks. Therefore, investigation of the production of fast ions during heating and of the subsequent fast ion behaviour in magnetically confined plasmas, together with an evaluation of the resulting bulk ion heating efficiency, are of essential importance for fusion reactor development. Gamma-ray diagnostics, based on the measurement of the gamma-ray emission from nuclear reactions between fast ions and the main plasma impurities, is a valuable technique for studying the fast particle energy distributions. Gamma-ray spectrometry provides information on the energy distribution, and the measurement of emission profiles supplies information on the spatial distribution of the reaction sites. Since 1987, the {gamma}-ray emission from JET plasmas has been systematically monitored and used successfully in the analysis of heating effects during ICRF and NBI heating in the JET tokamak. The classical character of the fast ion slowing down behaviour has been demonstrated and estimates have been obtained of the fast particle confinement time. The study of sawtooth crashes has demonstrated dramatic spatial redistribution of fast particles and other effects. In recent JET experiments to study the ITER-relevant ICRH scenarios ({sup 3}He)D and ({sup 3}He){sup 4}He, {gamma}-ray measurements provided information on the fast ion population, with the effective temperature of the energetic tail ions being deduced with the help of a {gamma}-ray spectrum simulation code, GAMMOD. In this paper, the main y-ray results are presented and the capabilities of gamma diagnostics are discussed in the light of the ITER-project programme.

  17. Operation and maintenance of nuclear power plant

    International Nuclear Information System (INIS)

    1990-04-01

    The proceedings contain 34 papers, almost all discussing specific problems or the Dukovany nuclear power plant. The major part is devoted to the matters of maintenance, regular and unplanned repairs, decontamination of the steam generator for inspection and repair purposes, various methods of in-service diagnostics. Some papers discuss reactor start-up, safety assurance, unit control and economic aspects. Environmental impacts of the power plant are also tackled. Some special contributions concern corrosion, chemical analysis of the coolant and the diagnostics of electrical equipment. The possibility is discussed of switching WWER reactors to improved fuel cycles with increased fuel burnup. (M.D.). 37 figs., 23 tabs., 47 refs

  18. The ITER poloidal field configuration and operation scenario

    International Nuclear Information System (INIS)

    Gribov, Y.; Portone, A.; Mondino, P.L.

    1995-01-01

    The ITER Poloidal Field (PF) system must satisfy the following requirements. (1) ITER must have a well-controlled, single null divertor magnetic configuration with nominal plasma current 21MA and moderate plasma elongation k95 < 1.65. (2) For a variety of plasma scenarios the ITER PF system must provide: inductive breakdown and start-up in an expanding-aperture limiter configuration near the outboard first wall; an inductive current ramp-up to the nominal plasma current with a reasonable assumption of resistive loss during current ramp-up; a pulse length of 1,000s for ignition and inductively-sustained burn at nominal plasma current; plasma shutdown (following fusion power termination) in a similar contracting-aperture limiter configuration. The present design of the PF system can satisfy the ITER requirements within specified limitations

  19. Optimising agile development practices for the maintenance operation: nine heuristics

    DEFF Research Database (Denmark)

    Heeager, Lise Tordrup; Rose, Jeremy

    2014-01-01

    Agile methods are widely used and successful in many development situations and beginning to attract attention amongst the software maintenance community – both researchers and practitioners. However, it should not be assumed that implementing a well-known agile method for a maintenance department...... is therefore a trivial endeavour - the maintenance operation differs in some important respects from development work. Classical accounts of software maintenance emphasise more traditional software engineering processes, whereas recent research accounts of agile maintenance efforts uncritically focus...... on benefits. In an action research project at Aveva in Denmark we assisted with the optimisation of SCRUM, tailoring the standard process to the immediate needs of the developers. We draw on both theoretical and empirical learning to formulate nine heuristics for maintenance practitioners wishing to go agile....

  20. Environmental management system for transportation maintenance operations : [technical brief].

    Science.gov (United States)

    2014-04-01

    This report provides the framework for the environmental management system to analyze : greenhouse gas emissions from transportation maintenance operations. The system enables user : to compare different scenarios and make informed decisions to minim...

  1. Constraints to private sector operation: maintenance of municipal infrastructure

    CSIR Research Space (South Africa)

    Wall, K

    2012-08-01

    Full Text Available This paper discusses the potential of the private sector to take medium- or longterm responsibility for the operation and/or maintenance of elements of infrastructure owned by municipalities....

  2. Franchising partnerships for roads engineering infrastructure operation and maintenance

    CSIR Research Space (South Africa)

    Wall, K

    2008-07-01

    Full Text Available This is a presentation delivered at the 27th SATC (Southern African Transport Conference) conference 2008, focusing on franchising principles and applying these principles to water services infrastructure, operation and maintenance...

  3. Innovative water service operation and maintenance: exploration of franchising partnerships

    CSIR Research Space (South Africa)

    Wall, K

    2008-10-01

    Full Text Available WRC and CSIR research has found that franchising partnerships could alleviate and address many challenges in the operation and maintenance of water services infrastructure. Franchising brings appropriate training to those on-site, and also offers...

  4. Maintenance and operations cost model for DSN subsystems

    Science.gov (United States)

    Burt, R. W.; Lesh, J. R.

    1977-01-01

    A procedure is described which partitions the recurring costs of the Deep Space Network (DSN) over the individual DSN subsystems. The procedure results in a table showing the maintenance, operations, sustaining engineering and supportive costs for each subsystems.

  5. Study on compact design of remote handling equipment for ITER blanket maintenance

    International Nuclear Information System (INIS)

    Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Shibanuma, Kiyoshi

    2006-03-01

    In the ITER, the neutrons created by D-T reactions activate structural materials, and thereby, the circumstance in the vacuum vessel is under intense gamma radiation field. Thus, the in-vessel components such as blanket are handled and replaced by remote handling equipment. The objective of this report is to study the compactness of the remote handling equipment (a vehicle/manipulator) for the ITER blanket maintenance. In order to avoid the interferences between the blanket and the equipment during blanket replacement in the restricted vacuum vessel, a compact design of the equipment is required. Therefore, the compact design is performed, including kinematic analyses aiming at the reduction of the sizes of the vehicle equipped with a manipulator handling the blanket and the rail for the vehicle traveling in the vacuum vessel. Major results are as follows: 1. The compact vehicle/manipulator is designed concentration on the reduction of the rail size and simplification of the guide roller mechanism as well as the reduction of the gear diameter for vehicle rotation around the rail. Height of the rail is reduced from 500 mm to 400 mm by a parameter survey for weight, stiffness and stress of the rail. The roller mechanism is divided into two simple functional mechanisms composed of rollers and a pad, that is, the rollers support relatively light loads during rail deployment and vehicle traveling while a pad supports heavy loads during blanket replacement. Regarding the rotation mechanism, the double helical gear is adopted, because it has higher contact ratio than the normal spur gear and consequently can transfer higher force. The smaller double helical gear, 996 mm in diameter, can achieve 26% higher output torque, 123.5 kN·m, than that of the original spur gear of 1,460 mm in diameter, 98 kN·m. As a result, the manipulator becomes about 30% lighter, 8 tons, than the original weight, 11.2 tons. 2. Based on the compact design of the vehicle/manipulator, the

  6. Virtual reality technology in nuclear power plant operation and maintenance

    International Nuclear Information System (INIS)

    Chen Sen

    2005-01-01

    In this paper a generic virtual reality comprehensive system focusing on the operation and maintenance in Nuclear Power Plant (NPP) is proposed. Under this layout, some key topics and means of the system are discussed. As example 'Virtual Nuclear Island' comprehensive system and its typical applications in NPP are set up. In the end, it prospects the applications of virtual reality technology in NPP operation, training and maintenance. (author)

  7. Remote Operation and Maintenance Demonstration Facility at ORNL

    International Nuclear Information System (INIS)

    Harvey, H.W.; Floyd, S.D; Kuban, D.P.; Singletary, B.H.; Stradley, J.G.

    1978-01-01

    The Remote Operation and Maintenance Facility is a versatile facility arranged to mock-up various hot-cell configurations. Modular units of simulated shielding and viewing windows were built to provide flexibility in arrangement. The facility is fully equipped with hoists, manipulators, television, and the other basic equipment and services necessary to provide capability for both remote operation and maintenance of several selected functional process equipment groups. 6 figures

  8. Computerization of operation and maintenance for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. Refs, figs and tabs.

  9. Operation and maintenance in the cooling and ventilation group

    OpenAIRE

    Bangert, N

    2003-01-01

    A core team of CERN staff is running the daily operations of the cooling and ventilation equipment at CERN, thus assuring multiple interfaces such as constant contact with the users of existing installations, the project leaders for new installations and intern-divisional communication. As support of this team, re-tendered contracts with external companies for the maintenance and operational tasks have been put into place multiple years ago. Higherlevel maintenance continues to be entrusted t...

  10. Remote operation and maintenance demonstration facility at ORNL

    International Nuclear Information System (INIS)

    Harvey, H.W.; Floyd, S.D.; Kuban, D.P.; Singletary, B.H.; Stradley, J.G.

    1978-01-01

    The Remote Operation and Maintenance Facility is a versatile facility arranged to mock up various hot cell configurations. Modular units of simulated shielding and viewing windows were built to provide flexibility in arrangement. The facility is fully equipped with hoists, manipulators, television, and other basic equipment and services necessary to provide capability for both remote operation and maintenance of several selected functional process equipment groups

  11. Computerization of operation and maintenance for nuclear power plants

    International Nuclear Information System (INIS)

    1995-07-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. Refs, figs and tabs

  12. Functional Problems and Maintenance Operations of Hydraulic Turbines

    Directory of Open Access Journals (Sweden)

    Liliana Topliceanu

    2016-02-01

    Full Text Available The exploitation in good conditions of the hydroelectric power plant imposes a rigorous maintenance of equipment and operating facilities, primarily of the turbine. The efficiency of the turbine is strongly affected by any defects which could occur during the operation. The paper makes a synthesis of the most frequent failures which have occurred during the functioning of Kaplan turbines plant and the required maintenance plan that has to be adopted. The maintenance rules for the optimal working of these turbines are also emphasized.

  13. On differential operators generating iterative systems of linear ODEs of maximal symmetry algebra

    Science.gov (United States)

    Ndogmo, J. C.

    2017-06-01

    Although every iterative scalar linear ordinary differential equation is of maximal symmetry algebra, the situation is different and far more complex for systems of linear ordinary differential equations, and an iterative system of linear equations need not be of maximal symmetry algebra. We illustrate these facts by examples and derive families of vector differential operators whose iterations are all linear systems of equations of maximal symmetry algebra. Some consequences of these results are also discussed.

  14. Task analysis of human-in-the-loop tele-operated maintenance: What can be learned from JET?

    International Nuclear Information System (INIS)

    Boessenkool, H.; Thomas, J.; Heemskerk, C.J.M.; Baar, M.R. de; Steinbuch, M.; Abbink, D.A.

    2014-01-01

    Highlights: •Maintenance task execution at JET was analyzed to guide improvements for ITER. •A large variation in task duration was found for various operator experience levels. •Results indicate significant room for improvement for tele-operated performance. •Improvent of visual feedback and artificial guiding forces was considered promising. -- Abstract: Remote maintenance will determine the available uptime of future fusion plants such as ITER. Experience at predecessor JET showed that a human-in-the-loop tele-operated approach is crucial, although this approach entails drawbacks such as the unavoidable extensive operator training and relatively long execution times. These drawbacks are common knowledge, but little quantitative research is available to guide improvements (such as improved training methods, or active operator support systems). The aim of this paper is to identify the key areas for further improvement of tele-operated maintenance. This is achieved by a detailed task analysis based on recent maintenance at JET, using task logbooks and video data as well as interviews with experienced master–slave operators. The resulting task analysis shows the (sub)tasks that were most time-consuming and shows a large variance in time performance within operators, but also substantial differences between qualified operators with different levels of experience. The operator interviews indicate that intuitive (virtual) visual feedback and artificial (guiding) forces are promising directions for improvement. The results found in this study will be used for future research and development activities focusing on haptic guiding strategies, with the aim to further design and optimize RH maintenance systems for ITER and beyond

  15. Operation and maintenance requirements of system design bases

    International Nuclear Information System (INIS)

    Banerjee, A.K.; Hanley, N.E.

    1989-01-01

    All system designs make assumptions about system operation testing, inspection, and maintenance. Existing industry codes and standards explicitly address design requirements of new systems, while issues related to system and plant reliability, life, design margins, effects of service conditions, operation, maintenance, etc., usually are implicit. However, system/component design documents of existing power plants often address the code requirements without considering the operation, maintenance, inspection, and testing (OMIT) requirements. The nuclear industry is expending major efforts at most nuclear power plants to reassemble and/or reconstitute system design bases. Stone ampersand Webster Engineering Corporation (SWEC) recently addressed the OMIT requirements of system/component design as an integral part of a utility's preventive maintenance program. For each component, SWEC reviewed vendor recommendations, NPRDS data/industry experience, the existing maintenance program, component service conditions, and actual plant experience. A maintenance program that considers component service conditions and plant experience ensures a connection between maintenance and design basis. Root cause analysis of failure and engineering evaluation of service condition are part of the program. System/component OMIT requirements also are compared against system design, service condition, degradation mechanism, etc., through system/component life-cycle evaluation

  16. Operation and maintenance results from ISFOC CPV plants

    Science.gov (United States)

    Gil, Eduardo; Martinez, María; de la Rubia, Oscar

    2017-09-01

    The analysis of field operation and maintenance data collected during a period of over eight years, from CPV installations consisting of three different CPV technologies (including second generation of one of these technologies), has allowed us to get valuable information about the long-term degradation of the CPV systems. Through the study of the maintenance control ratio previously defined and by applying the root cause analysis methodology, the components responsible for the most unplanned interventions for each technology were identified. Focusing maintenance efforts on these components, a reduction of the unplanned interventions and the total cost of maintenance has been achieved over the years. Therefore, the deployment of an effective maintenance plan, identifying critical components, is essential to minimize the risk for investors and maximize the CPV power plants lifetime and energy output, increasing the availability of CPV installations, boosting market confidence in CPV systems.

  17. Reliability analysis of maintenance operations for railway tracks

    International Nuclear Information System (INIS)

    Rhayma, N.; Bressolette, Ph.; Breul, P.; Fogli, M.; Saussine, G.

    2013-01-01

    Railway engineering is confronted with problems due to degradation of the railway network that requires important and costly maintenance work. However, because of the lack of knowledge on the geometrical and mechanical parameters of the track, it is difficult to optimize the maintenance management. In this context, this paper presents a new methodology to analyze the behavior of railway tracks. It combines new diagnostic devices which permit to obtain an important amount of data and thus to make statistics on the geometric and mechanical parameters and a non-intrusive stochastic approach which can be coupled with any mechanical model. Numerical results show the possibilities of this methodology for reliability analysis of different maintenance operations. In the future this approach will give important informations to railway managers to optimize maintenance operations using a reliability analysis

  18. Risk-based Operation and Maintenance for Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Nielsen, Jannie Jessen

    2011-01-01

    For offshore wind turbines, costs to Operation and Maintenance (OM) are substantial, and can be expected to increase when wind farms are placed at deeper water depths and in more harsh environments. Traditional strategies for OM include corrective and preventive (scheduled and condition...... statistics and costs of the different operations. The different OM strategies are described and compared in an illustrative example with focus on which types of information that are needed. Special focus is on comparison between risk-based maintenance strategies and the conventional maintenance planning...... and are often the driving mechanisms for failures / faults that need maintenance. Observations of the degree of damage can increase the reliability of predictions and decrease the costs of OM if integrated in a risk-based framework theoretically based on pre-posterior Bayesian decision theory. The mathematical...

  19. Remote operation and maintenance support services for nuclear power plants

    International Nuclear Information System (INIS)

    Yamamoto, Hiroki; Higuma, Koji; Shimizu, Shunichi; Sakuma, Masatake; Sonoda, Yukio; Kanemoto, Shigeru

    2004-01-01

    Toshiba Corporation constructed e-Toshiba Operating Plant Service (e-TOPS TM ) system and began remote operation and maintenance support service for nuclear power plants. The service put into practice remote operation and maintenance by harmony of information technologies such as internet and mobile, and nuclear power measurement/diagnostic technologies and security techniques. Outline of e-TOPS TM , remote-control service, -inspection system, -diagnostic service and technologies support service are explained. Construction, objects and application effects of e-TOPS TM , remote diagnostic system using image treatment techniques, construction of device record card control system are illustrated. (S.Y.)

  20. Chapter 8: Plasma operation and control [Progress in the ITER Physics Basis (PIPB)

    International Nuclear Information System (INIS)

    Gribov, Y.; Humphreys, D.; Kajiwara, K.; Lazarus, E.A.; Lister, J.B.; Ozeki, T.; Portone, A.; Shimada, M.; Sips, A.C.C.; Wesley, J.C.

    2007-01-01

    The ITER plasma control system has the same functional scope as the control systems in present tokamaks. These are plasma operation scenario sequencing, plasma basic control (magnetic and kinetic), plasma advanced control (control of RWMs, NTMs, ELMs, error fields, etc) and plasma fast shutdown. This chapter considers only plasma initiation and plasma basic control. This chapter describes the progress achieved in these areas in the tokamak experiments since the ITER Physics Basis (1999 Nucl. Fusion 39 2577) was written and the results of assessment of ITER to provide the plasma initiation and basic control. This assessment was done for the present ITER design (15 MA machine) at a more detailed level than it was done for the ITER design 1998 (21 MA machine) described in the ITER Physics Basis (1999 Nucl. Fusion 39 2577). The experiments on plasma initiation performed in DIII-D and JT-60U, as well as the theoretical studies performed for ITER, have demonstrated that, within specified assumptions on the plasma confinement and the impurity influx, ITER can produce plasma initiation in a low toroidal electric field (0.3 V m -1 ), if it is assisted by about 2 MW of ECRF heating. The plasma basic control includes control of the plasma current, position and shape-the plasma magnetic control, as well as control of other plasma global parameters or their profiles-the plasma performance control. The magnetic control is based on more reliable and simpler models of the control objects than those available at present for the plasma kinetic control. Moreover the real time diagnostics used for the magnetic control in many cases are more precise than those used for the kinetic control. Because of these reasons, the plasma magnetic control was developed for modern tokamaks and assessed for ITER better than the kinetic control. However, significant progress has been achieved in the plasma performance control during the last few years. Although the physics basis of plasma operation

  1. Human factors in operational maintenance on future naval vessels

    NARCIS (Netherlands)

    Post, W.M.; Schreurs, J.C.; Rakhorst-Oudendijk, M.L.W.; Badon Ghijben, N.A.; Diggelen, J. van

    2014-01-01

    The increasing complexity of operational maintenance on naval platforms and the need to sustain this also in battle conditions are in conflict with the requirement for crew reduction. This asks for a new approach. The Netherlands MoD knows how to develop technical solutions for operational

  2. 49 CFR 193.2713 - Training: operations and maintenance.

    Science.gov (United States)

    2010-10-01

    ... first-aid; and (3) All operating and appropriate supervisory personnel— (i) To understand detailed... 49 Transportation 3 2010-10-01 2010-10-01 false Training: operations and maintenance. 193.2713... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Personnel Qualifications and Training § 193.2713...

  3. Application of reliability centred maintenance to optimize operation and maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    2007-05-01

    In order to increase Member States capabilities in utilizing good engineering and management practices the Agency has developed a series of Technical Documents (TECDOCs) to describe best practices and members experience in the application of them. This TECDOC describes the concept of Reliability Centred Maintenance (RCM) which is the term used to describe a systematic approach to the evaluation, design and development of cost effective maintenance programmes for plant and equipment. The concept has been in existence for over 25 years originating in the civil aviation sector. This TECDOC supplements previous IAEA publications on the subject and seeks to reflect members experience in the application of the principles involved. The process focuses on the functionality of the plant and equipment and the critical failure mechanisms that could result in the loss of functionality. When employed effectively the process can result in the elimination of unnecessary maintenance activities and the identification and introduction of measures to address deficiencies in the maintenance programme. Overall the process can result in higher levels of reliability for the plant and equipment at reduced cost and demands on finite maintenance resources. The application of the process requires interaction between the operators and the maintenance practitioners which is often lacking in traditional maintenance programmes. The imposition of this discipline produces the added benefit of improved information flows between the key players in plant and equipment management with the result that maintenance activities and operational practices are better informed. This publication was produced within IAEA programme on nuclear power plants operating performance and life cycle management

  4. Improvement of operation and maintenance management

    International Nuclear Information System (INIS)

    Hamazaki, Kazushige

    1986-01-01

    The organization for the operation management of nuclear power plants was established by Japanese utilities, and it was shown in the high capacity ratio of nuclear power plants that the establishment of the organization was of value. The utilities have made much effort with the cooperation of regulatory bodies and plant manufacturers so as to be able to ensure the safe, stable operation of nuclear power plants by overcoming various technical and social problems, in order to obtain public confidence. The education and training of the personnel concerned with nuclear power generation are much to do with the special condition of nuclear power development in Japan. The development and history of the education and training of nuclear power staffs in Japanese utilities are reviewed in three phases, initial 1967 ∼ 1971, the period of upgrading the management and the technical level of nuclear power stations 1972 ∼ 1980, and the period of firmly established nuclear power generation thereafter. The important basic policy of the management in Japanese utility companies, the characteristics of the in-house education of staffs based on the basic policy and the education and training of technical staffs are reported. (Kako, I.)

  5. Iterative solution of nonlinear equations with strongly accretive operators

    International Nuclear Information System (INIS)

    Chidume, C.E.

    1991-10-01

    Let E be a real Banach space with a uniformly convex dual, and let K be a nonempty closed convex and bounded subset of E. Suppose T:K→K is a strongly accretive map such that for each f is an element of K the equation Tx=f has a solution in K. It is proved that each of the two well known fixed point iteration methods (the Mann and Ishikawa iteration methods) converges strongly to a solution of the equation Tx=f. Furthermore, our method shows that such a solution is necessarily unique. Explicit error estimates are given. Our results resolve in the affirmative two open problems (J. Math. Anal. Appl. Vol 151(2) (1990), p. 460) and generalize important known results. (author). 32 refs

  6. General Guidelines for Remote Operation and Maintenance of Pyroprocess Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Park, B. S.; Park, H. S.; Lee, H. J.; Choi, C. W.; Lee, J. K

    2007-12-15

    As the pyroprocess handle the high radioactive materials, a high radioactive material handling facility required high safety, radioactive shielding, strict quality control, and the remote handling equipment of high technology. This report describes the guidelines of for pyroprocess based the design guides for radioactive material handling facility and equipment from American Nuclear Society(ANS), design guidelines for remotely maintained equipment from Oak Ridge National Laboratory(ORNL), and the experience of design for ACP equipment installed at the ACPF(Advanced Conditioning Process Facility). The General guidelines in this report are as follows. The General guidelines for remote operation and maintenance of pyroprocess equipment: Pyroprocess, Remote handling equipment for pyroprocess, General guide for remote operation and maintenance, general guidelines for the design of remotely operated and maintained equipment, Estimation and analysis for remote maintenance.

  7. Operation and maintenance manual for data acquisition system of MIDAS

    International Nuclear Information System (INIS)

    Lee, D. Y.; Park, W. M.; Kim, J. T.; Euh, D. J.

    2001-09-01

    This report describes an operation and maintenance manual of the data acquisition system and the data processing system for the DVI performance evaluation facility, MIDAS. The data acquisition system is implemented with VXI based system of Kinetic Systems TM , and the data processing PC. This report presents the configuration method and operation procedure for the operator. The modification procedure and method for functional extension and performance modification are also included for the future demand

  8. Carlson iterating rational approximation and performance analysis of fractional operator with arbitrary order

    International Nuclear Information System (INIS)

    He Qiu-Yan; Yuan Xiao; Yu Bo

    2017-01-01

    The performance analysis of the generalized Carlson iterating process, which can realize the rational approximation of fractional operator with arbitrary order, is presented in this paper. The reasons why the generalized Carlson iterating function possesses more excellent properties such as self-similarity and exponential symmetry are also explained. K-index, P-index, O-index, and complexity index are introduced to contribute to performance analysis. Considering nine different operational orders and choosing an appropriate rational initial impedance for a certain operational order, these rational approximation impedance functions calculated by the iterating function meet computational rationality, positive reality, and operational validity. Then they are capable of having the operational performance of fractional operators and being physical realization. The approximation performance of the impedance function to the ideal fractional operator and the circuit network complexity are also exhibited. (paper)

  9. 78 FR 26383 - Environmental Assessment of the Proposed Increase in Operation, Maintenance and Replacement...

    Science.gov (United States)

    2013-05-06

    ... Proposed Increase in Operation, Maintenance and Replacement Activities Associated With the Wasatch County... of potential impacts associated with a proposed change in Operation, Maintenance and Replacement..., Maintenance, and Replacement Proposed Action includes: stabilizing canal banks; lining, piping, or enclosing...

  10. Vertical displacement events: a serious concern in future ITER operation

    International Nuclear Information System (INIS)

    Hassanein, A.; Sizyuk, T.; Ulrickson, M.

    2007-01-01

    The strongly elongated plasma configuration in ITER-like devices is vertically unstable unless an active control feedback at the vertical position is applied. A malfunction of this feedback system for variety of reasons can lead to a rapid plasma vertical displacement at full plasma current. As the plasma contacts the top or bottom of the vacuum vessel, the current is rapidly forced to zero, similar to the behavior of the plasma after the thermal quench of a disruption. This phenomenon constitutes the vertical displacement events (VDE). This can result in melting and vaporization of the plasma-facing component (PFC) as well as melting of the copper substrate and burnout of the coolant channels. The upgraded HEIGHTS simulation package is used to simulate in full 3D the response of an entire ITER module response to a VDE. The initial temperature distribution of the PFC and the bulk substrate prior to the VDE is calculated according to steady state heat flux, module design, and initial coolant temperature. The models used in the upgraded HEIGHTS were recently benchmarked against VDE simulation experiments using powerful electron beam and show an excellent agreement with the data.The surface temperature can then be very high and could result in significant melting of substrate copper and damage the coolant channels. In the case of Be surface, surface vaporization is quite high and will remove most incoming plasma power at typical ITER VDE condition. Therefore, the transmitted heat flux to the substrate and the coolant channels are low enough to cause any significant damage. However, if tungsten is exposed to the VDE the situation is quite different. No significant surface vaporization will occur at the tungsten surface thus, leaving the majority of the incident plasma power to be conducted to the copper substrate causing melting at the interface and burnout of coolant channel with serious implications on the integrity and subsequent performance of this module. The

  11. Design of casks: incorporating operational feedback from maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Bimet, F.; Hartenstein, M. [COGEMA Logistics, Saint Quentin (France)

    2004-07-01

    Casks are designed to conform to regulations and to client specifications. Essential areas such as easy operation, low costs of maintenance, low operation and maintenance doses, limited waste, are not explicitly covered. Notwithstanding, COGEMA LOGISTICS uses all feedback available, so that casks are designed to be easy, safe and economical to operate and maintain. Maintenance is an activity where you do spot items that old-time designers could have made better, and things that users should not have done. Thanks to quality assurance, there are a number of data available, waiting to be collected and exploited; they have to be identified, located, retrieved, and analysed. Using information such as wear, damage, use of spare parts, access problems helps to make casks ever better. It leads to more efficient concepts, and to upgrades on existing designs; it also allows to integrate environmental considerations, inter alia in the choice of materials and in maintenance methods. It is necessary for the designer to interact with the users, the cask owners, the maintenance providers, in order to gather all relevant information and events. This is made easier when all these actors are ''under one roof'', or have very close ties. This paper presents COGEMA LOGISTICS methods for collecting and analysing all these experiences waiting to be used. It explains our process for analysing data, preparing yearly reports that are made available to our designers. It describes how each new design is subject to a maintainability study, using this feedback, so that the cask safety is always assured, that radiological doses are kept to a minimum, and that operating and maintenance costs will remain as low as possible.

  12. Design of casks: incorporating operational feedback from maintenance

    International Nuclear Information System (INIS)

    Bimet, F.; Hartenstein, M.

    2004-01-01

    Casks are designed to conform to regulations and to client specifications. Essential areas such as easy operation, low costs of maintenance, low operation and maintenance doses, limited waste, are not explicitly covered. Notwithstanding, COGEMA LOGISTICS uses all feedback available, so that casks are designed to be easy, safe and economical to operate and maintain. Maintenance is an activity where you do spot items that old-time designers could have made better, and things that users should not have done. Thanks to quality assurance, there are a number of data available, waiting to be collected and exploited; they have to be identified, located, retrieved, and analysed. Using information such as wear, damage, use of spare parts, access problems helps to make casks ever better. It leads to more efficient concepts, and to upgrades on existing designs; it also allows to integrate environmental considerations, inter alia in the choice of materials and in maintenance methods. It is necessary for the designer to interact with the users, the cask owners, the maintenance providers, in order to gather all relevant information and events. This is made easier when all these actors are ''under one roof'', or have very close ties. This paper presents COGEMA LOGISTICS methods for collecting and analysing all these experiences waiting to be used. It explains our process for analysing data, preparing yearly reports that are made available to our designers. It describes how each new design is subject to a maintainability study, using this feedback, so that the cask safety is always assured, that radiological doses are kept to a minimum, and that operating and maintenance costs will remain as low as possible

  13. Ethernet Operation Administration and Maintenance ; Opportunities for the NREN community

    NARCIS (Netherlands)

    Prins, M.J.; Malhotra, R.

    2011-01-01

    Ethernet started its life as a Local Area Network technology and initially did not have Operations, Administration and Maintenance (OAM) features like IP Ping, IP Traceroute and SDH Loss of Frame. Monitoring and management was mainly done on the IP level. In the case of delivery of Ethernet

  14. RA Reactor operation and maintenance (I-IX), Part I

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-12-01

    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

  15. Operations and Maintenance Manual, Atmospheric Contaminant Sensor, Revision B.

    Science.gov (United States)

    National Aeronautics and Space Administration, Washington, DC.

    The sensor is a mass spectrometer system which continuously monitors the atmospheric constituents of hydrogen, water vapor, nitrogen, oxygen, and carbon dioxide, and monitors the Freons on a demand sampling basis. The manual provides a system description, operational procedures, and maintenance and troubleshooting instructions. Circuit diagrams…

  16. Planning of operation & maintenance using risk and reliability based methods

    DEFF Research Database (Denmark)

    Florian, Mihai; Sørensen, John Dalsgaard

    2015-01-01

    Operation and maintenance (OM) of offshore wind turbines contributes with a substantial part of the total levelized cost of energy (LCOE). The objective of this paper is to present an application of risk- and reliability-based methods for planning of OM. The theoretical basis is presented...

  17. Maintenance, repair and operation (MRO) of shutdown facilities

    International Nuclear Information System (INIS)

    Kenny, S.

    2006-01-01

    What level of maintenance does one apply to a shutdown facility? Well it depends on who you ask. Operations staff sees facilities that have completed their useful life cycle as a cost drain while Decommissioning staff sees this as the start of a new life cycle. Based on the decommissioning plan for the particular facility the building could complete another full life cycle while under decommissioning whether it is in storage with surveillance mode or under active decommissioning. This paper will explore how you maintain a facility and systems for many years after its useful life until final decommissioning is completed. When a building is declared redundant, who looks after it until the final decommissioning end state is achieved? At the AECL, Chalk River Labs site the safe shutdown and turnover process is one key element that initiates the decommissioning process. The real trick is orchestrating maintenance, repair and operation plans for a facility that has been poorly invested in during its last years of useful life cycle. To add to that usually shutdowns are prolonged for many years beyond the expected turnover period. During this presentation I will cover what AECL is doing to ensure that the facilities are maintained in a proper state until final decommissioning can be completed. All facilities or systems travel through the same life cycle, design, construction, commissioning, operation, shutdown and demolition. As we all know, nuclear facilities add one more interesting twist to this life cycle called Decommissioning that lands between shutdown and demolition. As a facility nears the shutdown phase, operations staff loose interest in the facility and stop investing in upgrades, repairs and maintenance but continue to invest and focus on maximizing operations. Facility maintenance standards produced by the International Facility Maintenance Association (IFMA) based on a survey done every year state that 2.2% of the total operating costs for the site should be

  18. Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance

    International Nuclear Information System (INIS)

    Doyle, E. Kevin

    2002-01-01

    As previously reported at ICONE 6 in New Orleans, 1996, and ICONE 9 in Niece, 2001, the use of various maintenance optimization techniques at Bruce has lead to cost effective preventive maintenance applications for complex systems. Innovative practices included greatly reducing Reliability Centered Maintenance (RCM) costs while maintaining the accuracy of the analysis. The optimization strategy has undergone further evolution and at the present an Integrated Maintenance Program (IMP) is being put in place. Further cost refinement of the station preventive maintenance strategy whereby decisions are based on statistical analysis of historical failure data is being evaluated. A wide range of Operational Research (OR) literature was reviewed for implementation issues and several encouraging areas were found that will assist in the current effort of evaluating maintenance optimization techniques for nuclear power production. The road ahead is expected to consist first of resolving 25 years of data issues and preserving the data via appropriate knowledge system techniques while post war demographics permit experts to input into the system. Subsequent analytical techniques will emphasize total simplicity to obtain the requisite buy in from Corporate Executives who possibly are not trained in Operational Research. Case studies of containment airlock seal failures are used to illustrate the direct applicability of stochastic processes. Airlocks and transfer chambers were chosen as they have long been known as high maintenance items. Also, the very significant financial consequences of this type of failure will help to focus the attention of Senior Management on the effort. Despite substantial investment in research, improvement in the design of the seal material or configuration has not been achieved beyond the designs completed in the 1980's. Overall, the study showed excellent agreement of the relatively quick stochastic methods with the maintenance programs produced at

  19. Advances in new WWER designs to improve operation and maintenance

    International Nuclear Information System (INIS)

    Dragunov, Y.G.; Ryzhov, S.B.; Podshibiakin, A.K.; Vasilchenko, I.N.; Repin, A.I.; Nikitenko, M.P.; Konoplev, N.P.; Fil, N.S.

    2000-01-01

    Economic operational indices of WWER-type reactors show their competitiveness in all the countries where these reactors operate. Advanced WWERs being designed and constructed now have the improved characteristics of economical efficiency and are more convenient for operation and maintenance. Many technical solutions aimed at improvement of the operational performance are implemented in the design of WWER-1000/V-392 and WWER-640/V-407, and these reactors are the important basis for the nuclear power expansion in Russia. Some of these solutions are considered in the present paper. (author)

  20. Assessment of alternative vessel and blanket design on ITER operation

    Energy Technology Data Exchange (ETDEWEB)

    Cavinato, M., E-mail: mario.cavinato@f4e.europa.e [FUSION FOR ENERGY Joint Undertaking, 08019 Barcelona (Spain); Portone, A.; Saibene, G.; Sartori, R. [FUSION FOR ENERGY Joint Undertaking, 08019 Barcelona (Spain); Albanese, R.; Ambrosino, G.; Ariola, M. [Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Napoli (Italy); Artaserse, G. [Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Reggio Calabria (Italy); Mattei, M. [Associazione Euratom-ENEA-CREATE, DIAM, Seconda Universita di Napoli, Via Roma 29, Aversa, CE 81031 Italy (Italy); Pironti, A. [Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Napoli (Italy); Villone, F. [Associazione Euratom-ENEA-CREATE, DIMET, Universita degli Studi di Cassino (Italy)

    2010-12-15

    In the framework of the ITER project, an investigation has been conducted on an alternative vessel and blanket design, aimed at reducing cost and production risk. The modifications proposed have a strong impact on plasma control since they affect the main conducting structures surrounding the plasma column, providing passive stabilization but at the same time shielding the field generated by the active coils to control the plasma motion and shape. An extensive analysis was performed to assess the plasma vertical controllability and the modified requirements to the in-vessel vertical stability coils system as well as to the external Poloidal Field coils system. A similar analysis was aimed at assessing the performance of the shape control system in presence of the modified structures. The effect on plasma breakdown was also evaluated in terms of maximum initial loop voltage, quality of magnetic null and the flux loss related to the breakdown delay that was quantified under the same hypothesis employed by ITER for the baseline design. Furthermore, the modified design presents issues for the magnetic diagnostic system, related to the shielding of the probes by the eddy currents, which were analysed with a 3D model. The results of the analyses performed have some general interest in particular regarding the influence on plasma stability of 3D structures with close proximity to the plasma. The present paper aims at giving an overview of the analyses that have been carried out and a summary of the results in terms of impact of the modified design on plasma control and scenario, and in general an evaluation of the role of passive structure in plasma vertical stability and shape control.

  1. ELECTRIC MOTORS MAINTENANCE PLANNING FROM ITS OPERATING VARIABLES

    Directory of Open Access Journals (Sweden)

    Francisco RODRIGUES

    2017-07-01

    Full Text Available The maintenance planning corresponds to an approach that seeks to maximize the availability of equipment and, conse-quently, increase the levels of competitiveness of companies by increasing production times. This paper presents a maintenance planning based on operating variables (number of hours worked, duty cycles, number of revolutions to maximizing the availability of operation of electrical motors. The reading of the operating variables and its sampling is done based on predetermined sampling cycles and subsequently is made the data analysis through time series algo-rithms aiming to launch work orders before reaching the variables limit values. This approach is supported by tools and technologies such as logical applications that enable a graphical user interface for access to relevant information about their Physical Asset HMI (Human Machine Interface, including the control and supervision by acquisition through SCADA (Supervisory Control And data acquisition data, also including the communication protocols among different logical applications.

  2. Electric Motors Maintenance Planning From Its Operating Variables

    Science.gov (United States)

    Rodrigues, Francisco; Fonseca, Inácio; Farinha, José Torres; Ferreira, Luís; Galar, Diego

    2017-09-01

    The maintenance planning corresponds to an approach that seeks to maximize the availability of equipment and, consequently, increase the levels of competitiveness of companies by increasing production times. This paper presents a maintenance planning based on operating variables (number of hours worked, duty cycles, number of revolutions) to maximizing the availability of operation of electrical motors. The reading of the operating variables and its sampling is done based on predetermined sampling cycles and subsequently is made the data analysis through time series algorithms aiming to launch work orders before reaching the variables limit values. This approach is supported by tools and technologies such as logical applications that enable a graphical user interface for access to relevant information about their Physical Asset HMI (Human Machine Interface), including the control and supervision by acquisition through SCADA (Supervisory Control And data acquisition) data, also including the communication protocols among different logical applications.

  3. Maintenance Issues in Long Term Operation of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Contri, P.; Bieth, M.; Rieg, C.

    2006-01-01

    Due to current social and economical framework, in last years many nuclear power plant owners started a program for the Long Term Operation (LTO)/PLEX (Plant Life Extension) of their older nuclear facilities. This process has many nuclear safety implications, other than strategic and political ones. The need for tailoring the available safety assessment tools to such applications has become urgent in recent years and triggered many research actions. The review of regular maintenance and ageing management programs are tools widely used in LTO/PLEX context in many Countries. However, most of these tools are rather general and in many cases they need reshaping in an LTO/PLEX framework before application, with focus to the safety implications of the LTO/PLEX. Many Countries and plants radically modified their maintenance rules towards a condition based approach as a precondition for the implementation of LTO/PLEX programs. In 2004 a network of European Organisations operating Nuclear Power Plants, SENUF, under the coordination of the JRC-IE, carried out an extensive questionnaire on maintenance practice in their facilities aiming at capturing the aspects of the maintenance programs where research is mostly needed. This paper uses some results of the questionnaire, which was not oriented to LTO/PLEX, to draw some conclusions on how the current maintenance programs could support a potential LTO/PLEX, among the other programs running at NPPs. In this sense, it is spin-off of the SENUF WG on maintenance. The paper aims at identifying the technical attributes of the maintenance programs more directly affecting the decision for a long-term safe operation of a nuclear facility, the issues related to their implementation and safety review. The paper includes an analysis of the questionnaire circulated among the SENUF participants and a discussion on the implications of optimised maintenance programs in existing plants. Some examples at WWER plants taken by sources other than

  4. Development on JET of Advanced Tokamak Operations for ITER

    International Nuclear Information System (INIS)

    Tuccillo, A.A.; Crisanti, F.; Litaudon, X.

    2005-01-01

    Recent research on Advanced Tokamak in JET has focused on scenarii with both monotonic and reversed shear q profiles having plasma parameters as relevant as possible for extrapolation to ITER. Wide ITBs, R∼3.7m, are formed at ITER relevant triangularity δ∼0.45, with n e /n G ∼60% and ELMs moderated by Ne injection. At higher current (I P ≤3.5MA, δ∼0.25) wide ITBs sitting at R≥ 3.5m (positive shear region) have been developed, generally MHD events terminate these barrier otherwise limited in strength by power availability. ITBs with core density close to Greenwald value are obtained with plasma target preformed by opportune timing of LHCD, pellet injection and small amount of NBI power. ITB start with toroidal rotation 4 times lower than the standard NBI heated ITBs. Full CD is achieved in reversed shear ITBs at 3T/1.8 MA, by using 10MW NBI, 5MW ICRH and 3MW LH. Wide ITBs located at R=3.6m, without impurity accumulation and type-III ELMs edge can be sustained for a time close to neo-classical resistive time. These discharges have been extended to the maximum duration allowed by subsystems (20s) with the JET record of injected energy: E∼330 MJ. Integrated control of pressure and current profile isit; feature used in these discharges. Central ICRF mode conversion electron heating, added to about 14MW NBI power, produced impressive ITBs with equivalent Q DT ∼ 0.25. Conversely ion ITBs are obtained with low torque injection, by ICRH 3 He minority heating of ions, on pure LHCD electron ITBs. Similarity experiments between JET and AUG have compared the dynamics of ITBs and have been the starting point of Hybrid Scenarios activity, then developed at ρ* as low as ρ*∼3*10 -3 . The development of hybrid regime with dominant electron heating has also started. Injection of trace of tritium and a mixture of Ar/Ne allowed studying fuel and impurities transport in many of the explored AT scenarios. (author)

  5. Standard hydrogen monitoring system-B operation and maintenance manual

    International Nuclear Information System (INIS)

    Bender, R.M.

    1995-01-01

    The purpose of this document is to provide information for the operation and maintenance of the Standards Hydrogen Monitoring System-B (SHMS-B) used in the 200E and 200W area tank farms on the Hanford site. This provides information specific to the mechanical operation of the system and is not intended to take the place of a Plant Operating Procedure. The primary function of the SHMS-B is to monitor specifically for hydrogen in the waste tank vapor space which may also contain unknown quantities of other gaseous constituents

  6. NPP operation and maintenance with french-built NPPs

    International Nuclear Information System (INIS)

    Mira, J.J.

    1987-01-01

    In Frace, 80% of the electricity production will be nuclear in 1990. More than to-day, PWR units will be operated by ELECTRICITE DE FRANCE on a load-follow basis. Every effort is made to reduce planned and forced outages. Maintenance is shared between EDF and FRAMATOME, the latter being in charge of high technology operations. All these actions are eased by the standardization of units, within each power class, the resulting build-up of experience being available to all PWR operators in the world, more particularly to those of FRAMATOME-built units

  7. 40 CFR 63.1447 - What are my operation and maintenance requirements?

    Science.gov (United States)

    2010-07-01

    ... corrective action according to written procedures specified in your operation and maintenance plan to... 40 Protection of Environment 12 2010-07-01 2010-07-01 true What are my operation and maintenance... Maintenance Requirements § 63.1447 What are my operation and maintenance requirements? (a) As required by § 63...

  8. 40 CFR 63.7300 - What are my operation and maintenance requirements?

    Science.gov (United States)

    2010-07-01

    ...-term maintenance. (3) Corrective action for all baghouses applied to pushing emissions. In the event a... 40 Protection of Environment 13 2010-07-01 2010-07-01 false What are my operation and maintenance... Battery Stacks Operation and Maintenance Requirements § 63.7300 What are my operation and maintenance...

  9. Mechanical design issues associated with mounting, maintenance, and handling of an ITER divertor

    International Nuclear Information System (INIS)

    Goranson, D.L.; Fogarty, D.J.; Jones, G.H.

    1992-01-01

    Several designs that address plasma-facing plate configurations and thermal-hydraulic design issues have been developed for the ITER divertor. Design criteria growing out of physics requirements, physical constraints, and remote handling requirements impose severe mechanical requirements on the support structure and its attachments. These pose a challenge to the mechanical design of a divertor, which must be addressed before a functional divertor is practical that is, one that can be remotely handled, aligned, and maintained; that functions reliably under thermal loading and disruptions; and that gives the required life in the nuclear environment predicted for ITER. This paper discusses the design criteria for the divertor mounting structure and identifies the mechanical design issues that need to be addressed

  10. The ITER EC H and CD Upper Launcher: Analysis of vertical Remote Handling applied to the BSM maintenance

    International Nuclear Information System (INIS)

    Grossetti, Giovanni; Aiello, Gaetano; Heemskerk, Cock; Elzendoorn, Ben; Geßner, Robby; Koning, Jarich; Meier, Andreas; Ronden, Dennis; Späh, Peter; Scherer, Theo; Schreck, Sabine; Strauß, Dirk; Vaccaro, Alessandro

    2013-01-01

    This paper deals with Remote Handling activities foreseen on the Blanket Shield Module, the plasma facing component of the ITER Electron Cyclotron Heating and Current Drive Upper Launcher. The maintenance configuration considered here is the Vertical Remote Handling, meaning gravity acting along the launcher radial axis. The plant, where the maintenance under consideration is occurring, is the Hot Cell Facility Work Cell. The study here reported has been carried out within the presently ongoing EFDA Goal Oriented Training program on Remote Handling (GOT-RH), which aims to support ITER activities. This document and its contents have to be considered as part of a more vast RAMI analysis to be developed within the GOT-RH, which aims to maximize the Electron Cyclotron Heating and Current Drive system availability. The Baseline CAD model of the Electron Cyclotron Heating and Current Drive Upper Launcher is currently in its preliminary design phase and does not provide enough details for developing a fully detailed maintenance strategy. Therefore, through a System Engineering approach, a set of assumptions was conceived on the launcher structure, as a basis for development of a Remote Handling strategy. Moreover, to compare different design solutions related to the possibility of integrating a quasi-optical component into the Blanket Shield Module, a Trade-Off was made, and its contents are shown here. The outcome of this System Engineering approach has been formalized into Task Definition Forms whose contents are reported here. The Remote Handling strategy presented in this work will be tested in the near future both through Virtual Reality simulations and through prototype experiments

  11. The ITER EC H and CD Upper Launcher: Analysis of vertical Remote Handling applied to the BSM maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Grossetti, Giovanni, E-mail: giovanni.grossetti@kit.edu [Karlsruhe Institute of Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Aiello, Gaetano [Karlsruhe Institute of Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Heemskerk, Cock [Heemskerk Innovative Technology, Merelhof 2, 2172 HZ Sassenheim (Netherlands); Elzendoorn, Ben [FOM Institute DIFFER, P.O. Box 1207, 3430 BE Nieuwegein (Netherlands); Geßner, Robby [Karlsruhe Institute of Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Koning, Jarich [Heemskerk Innovative Technology, Merelhof 2, 2172 HZ Sassenheim (Netherlands); Meier, Andreas [Karlsruhe Institute of Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany); Ronden, Dennis [FOM Institute DIFFER, P.O. Box 1207, 3430 BE Nieuwegein (Netherlands); Späh, Peter; Scherer, Theo; Schreck, Sabine; Strauß, Dirk; Vaccaro, Alessandro [Karlsruhe Institute of Technology, Association KIT-EURATOM, P.O. Box 3640, D-76021 Karlsruhe (Germany)

    2013-10-15

    This paper deals with Remote Handling activities foreseen on the Blanket Shield Module, the plasma facing component of the ITER Electron Cyclotron Heating and Current Drive Upper Launcher. The maintenance configuration considered here is the Vertical Remote Handling, meaning gravity acting along the launcher radial axis. The plant, where the maintenance under consideration is occurring, is the Hot Cell Facility Work Cell. The study here reported has been carried out within the presently ongoing EFDA Goal Oriented Training program on Remote Handling (GOT-RH), which aims to support ITER activities. This document and its contents have to be considered as part of a more vast RAMI analysis to be developed within the GOT-RH, which aims to maximize the Electron Cyclotron Heating and Current Drive system availability. The Baseline CAD model of the Electron Cyclotron Heating and Current Drive Upper Launcher is currently in its preliminary design phase and does not provide enough details for developing a fully detailed maintenance strategy. Therefore, through a System Engineering approach, a set of assumptions was conceived on the launcher structure, as a basis for development of a Remote Handling strategy. Moreover, to compare different design solutions related to the possibility of integrating a quasi-optical component into the Blanket Shield Module, a Trade-Off was made, and its contents are shown here. The outcome of this System Engineering approach has been formalized into Task Definition Forms whose contents are reported here. The Remote Handling strategy presented in this work will be tested in the near future both through Virtual Reality simulations and through prototype experiments.

  12. Standard Hydrogen Monitoring System-D operation and maintenance manual

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1997-01-01

    The purpose of this document is to provide information for the operation and maintenance of the Standard Hydrogen Monitoring System-D (SHMS-D) used in the 200E and 200W area tank farms on the Hanford Site. This provides information specific to the mechanical operation of the system and is not intended to take the place of a Plant Operating Procedure. However, it does provide more information on the system than a Plant Operating Procedure. The intent here is that the system is started up by a technician or engineer who has completed tank farms training course No. 351405, and then the only actions performed by Operations will be routine log taking. If any problems not addressed by the operating procedure are encountered with the unit, engineering should be contacted

  13. Standard hydrogen monitoring system - E operation and maintenance manual

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1997-01-01

    The purpose of this document is to provide information for the operation and maintenance of the Standard Hydrogen Monitoring System- E (SHMS-E) used in the 200E and 20OW area tank farms on the Hanford Site. This provides information specific to the mechanical operation of the system and is not intended to take the place of a Plant Operating Procedure. However, it does provide more information on the system than a Plant Operating Procedure. The intent here is that the system is started up by a technician or engineer who has completed tank farms training course for SHMS, and then the only actions performed by Operations will be routine log taking. If any problems not addressed by the operating procedure are encountered with the unit, engineering should be contacted

  14. Operations and maintenance plan : Dallas Integrated Corridor Management (ICM) demonstration project.

    Science.gov (United States)

    2014-01-01

    This Operations and Maintenance (O&M) Plan describes how the Integrated Corridor Management System (ICMS) will be used in daily transportation operations and maintenance activities. The Plan addresses the activities needed to effectively operate the ...

  15. Longview District Operations and Maintenance Headquarters: Environmental assessment

    International Nuclear Information System (INIS)

    1992-03-01

    Bonneville Power Administration (BPA) operations and maintenance staff are presently based at a headquarters next to the Longview Substation. These headquarters buildings, however, were built in 1941 and have deteriorated to the point of needing extensive repair. They also lack sufficient inside storage space. New buildings cannot be constructed on the site because of surrounding development. In addition, the site is within an area exposed to industrial fallout (coal tar pitch and metallic particles) that may be damaging buildings, equipment, and vehicles. BPA is concerned about the potential health risk to headquarters staff from the fallout. In light of these problems, BPA proposes to construct a new operations and maintenance headquarters at a different location, and to demolish the existing headquarters. This paper discusses the environmental impacts of the proposed action and alternatives

  16. New Trends in the Outsourcing of Maintenance/Operation Services

    CERN Document Server

    Wilhelmsson, M

    2001-01-01

    The contracting-experience of maintenance/operation work in our group can today be considered as rich with the first generation of contract implemented more than 15 years ago. The incumbent contract was started in 1997, so it is now into its 4th year. Certain improvements that have already been implemented has had a large impact on our contract culture e.g. performance indicators. The next re-tendering is now approaching and with this borne in mind, the author will discuss through various sections of this report the following main points: firstly, an overview of the trends today in this area; secondly, comparing these trends with implemented practices; and finally, what can be future development in the outsourcing of the maintenance/operation of the Cooling & Ventilation services.

  17. Kaunas gas, Lithuania. Operation and maintenance report. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The main objective of this project was to transfer knowledge accumulated in Denmark about modern techniques of natural gas distribution to employees of the Lithuanian gas sector by informing them about modern measuring equipment and evaluating the results. The main objectives were: To improve the efficiency of maintenance and repair works of the distribution network in Kaunas; To decrease the number of leakages and to improve the operation of the cathodic protection system; To ensure protection of the pipelines and to avoid damages on other constructions and installations. The project consisted of four components which will all exert an influence on the future rehabilitation of steel pipe networks in the gas sector of Lithuania. The components were the following: Preparation of Operation and Maintenance Manual for Kaunas Gas Company; Cathodic measuring and pilot investigation; Analysis and improvement of the organisation of the Kaunas Gas Company; Training material for cathodic protection in Lithaunia. (au)

  18. Design requirements, operation and maintenance of gas-cooled reactors

    International Nuclear Information System (INIS)

    1989-06-01

    At the invitation of the Government of the USA the Technical Committee Meeting on Design Requirements, Operation and Maintenance of Gas-Cooled Reactors, was held in San Diego on September 21-23, 1988, in tandem with the GCRA Conference. Both meetings attracted a large contingent of foreign participants. Approximately 100 delegates from 18 different countries participated in the Technical Committee meeting. The meeting was divided into three sessions: Gas-cooled reactor user requirement (8 papers); Gas-cooled reactor improvements to facilitate operation and maintenance (10 papers) and Safety, environmental impacts and waste disposal (5 papers). A separate abstract was prepared for each of these 23 papers. Refs, figs and tabs

  19. Preparation of acceptance tests and criteria for the Test Blanket Systems to be operated in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Cuquel, B. [AIRBUS Defence and Space S.A.S., 13115 Saint Paul Lez Durance (France); Demange, D.; Ghidersa, B.-E. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Giancarli, L.M.; Iseli, M.; Jourdan, T. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Pascal, R.; Ring, W. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

    2015-10-15

    Highlights: • Initial guideline for acceptance testing and acceptance criteria for Test Blanket Systems in ITER. • These tests complement those required by the applicable codes and standards, and regulations. • Completion of TBS manufacture will be followed by Factory Acceptance Testing, prior to shipment. • Next steps are “Reception Inspection Tests”, and on-site pre-installation and components tests. • This guideline allows the detailing of the TBS specific test plans and their scheduling. - Abstract: This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for the TBS, starting from the end-product at the ITER Members factories, and to generally define the type of tests that have to be performed on the ITER site after shipment, and/or prior to the systems final commissioning phase.

  20. Automatic and manual operation modes of the TFTR maintenance manipulator

    International Nuclear Information System (INIS)

    Boehme, G.; Gumb, L.; Lotz, E.; Mueller, G.; Selig, M.

    1987-01-01

    The remote in-vessel operations scheduled to maintain the TFTR at Princeton, NJ, USA, comprise inspection, calibration, cleaning and protective tile replacement. The environmental conditions inside the torus vessel are ultra high vacuum, moderate γ-radiation and 150 0 C temperature of the vessel structure. The Princeton Plasma Physics Laboratory (PPPL) and KfK are jointly developing a maintenance manipulator (MM) which can perform these tasks. (orig./HP)

  1. Logistics Operations Management Center: Maintenance Support Baseline (LOMC-MSB)

    Science.gov (United States)

    Kurrus, R.; Stump, F.

    1995-01-01

    The Logistics Operations Management Center Maintenance Support Baseline is defined. A historical record of systems, applied to and deleted from, designs in support of future management and/or technical analysis is provided. All Flight elements, Ground Support Equipment, Facility Systems and Equipment and Test Support Equipment for which LOMC has responsibilities at Kennedy Space Center and other locations are listed. International Space Station Alpha Program documentation is supplemented. The responsibility of the Space Station Launch Site Support Office is established.

  2. Use of passive systems to improve plant operation and maintenance

    International Nuclear Information System (INIS)

    Shah, D.

    2000-01-01

    In a deregulated future, a utility's strength will depend on its ability to be cost competitive in the marketplace. However, the competitive advantage of nuclear power will depend on each owner's ability to reduce Operating and Maintenance (O and M) costs without sacrificing nuclear safety. The use of passive systems (i.e., systems without any moving parts) can reduce plant O and M costs while increasing safety in nuclear power plants. (author)

  3. Operation and maintenance techniques of cranes and Hoist in IMEF

    International Nuclear Information System (INIS)

    Soong, Woong Sup; Oh, Yon Woo; Ahn, Sang Bock; Park, Dae Gue; Whang, Ryoung Wha

    1999-07-01

    Crane and hoist of 11 sets are installed int the Irradiated Material Examination Facility (IMEF). IMEF is divided into two parts such as hot cell area and service area. 30/5-ton overhead crane is installed in service area for transfer of irradiated material transportation cask and other several kinds of heavy equipment. This report describes maintenance techniques, repair procedure, daily and special checking list, which will ensure safety in routine operation and even in abnormality. (author). 8 refs

  4. Operation and maintenance techniques of cranes and Hoist in IMEF

    Energy Technology Data Exchange (ETDEWEB)

    Soong, Woong Sup; Oh, Yon Woo; Ahn, Sang Bock; Park, Dae Gue; Whang, Ryoung Wha

    1999-07-01

    Crane and hoist of 11 sets are installed int the Irradiated Material Examination Facility (IMEF). IMEF is divided into two parts such as hot cell area and service area. 30/5-ton overhead crane is installed in service area for transfer of irradiated material transportation cask and other several kinds of heavy equipment. This report describes maintenance techniques, repair procedure, daily and special checking list, which will ensure safety in routine operation and even in abnormality. (author). 8 refs.

  5. Development of a control system for a heavy object handling manipulator. Application to a remote maintenance system for ITER blanket module

    International Nuclear Information System (INIS)

    Yoshimi, Takashi; Tsuji, Kouichi; Miyagawa, Shinichi; Kubo, Tomomi; Kakudate, Satoshi; Tada, Eisuke

    2001-01-01

    This paper describes a control system for the heavy object handling manipulator. It has been developed for the blanket module remote maintenance system of ITER (International Thermonuclear Fusion Experimental Reactor). A rail-mounted vehicle-type manipulator is proposed for the precise handling of a blanket module which is about 4 tons in weight. Basically, this manipulator is controlled by teaching-playback technique. When grasping or releasing the module, the manipulator sags and the position of the end-effector changes about 50 [mm]. Applying only the usual teaching-playback control makes the smooth operation of setting/removing modules to/from the vacuum vessel wall difficult due to this position change. To solve this proper problem of heavy object handling manipulator, we have developed a system which uses motion patterns generated from two kinds of teaching points. These motion patterns for setting/removing heavy objects are generated by combining teaching points for positioning the manipulator with and without grasping the object. When these motion patterns are applied, the manipulator can transfer the object's weight smoothly at the setting/removing point. This developed system has been applied to the real-scale mock-up of the vehicle manipulator and through the actual module setting/removing experiments, we have verified its effectiveness and realized smooth maintenance operation. (author)

  6. Identifying Human Factors Issues in Aircraft Maintenance Operations

    Science.gov (United States)

    Veinott, Elizabeth S.; Kanki, Barbara G.; Shafto, Michael G. (Technical Monitor)

    1995-01-01

    Maintenance operations incidents submitted to the Aviation Safety Reporting System (ASRS) between 1986-1992 were systematically analyzed in order to identify issues relevant to human factors and crew coordination. This exploratory analysis involved 95 ASRS reports which represented a wide range of maintenance incidents. The reports were coded and analyzed according to the type of error (e.g, wrong part, procedural error, non-procedural error), contributing factors (e.g., individual, within-team, cross-team, procedure, tools), result of the error (e.g., aircraft damage or not) as well as the operational impact (e.g., aircraft flown to destination, air return, delay at gate). The main findings indicate that procedural errors were most common (48.4%) and that individual and team actions contributed to the errors in more than 50% of the cases. As for operational results, most errors were either corrected after landing at the destination (51.6%) or required the flight crew to stop enroute (29.5%). Interactions among these variables are also discussed. This analysis is a first step toward developing a taxonomy of crew coordination problems in maintenance. By understanding what variables are important and how they are interrelated, we may develop intervention strategies that are better tailored to the human factor issues involved.

  7. SUMO: operation and maintenance management web tool for astronomical observatories

    Science.gov (United States)

    Mujica-Alvarez, Emma; Pérez-Calpena, Ana; García-Vargas, María. Luisa

    2014-08-01

    SUMO is an Operation and Maintenance Management web tool, which allows managing the operation and maintenance activities and resources required for the exploitation of a complex facility. SUMO main capabilities are: information repository, assets and stock control, tasks scheduler, executed tasks archive, configuration and anomalies control and notification and users management. The information needed to operate and maintain the system must be initially stored at the tool database. SUMO shall automatically schedule the periodical tasks and facilitates the searching and programming of the non-periodical tasks. Tasks planning can be visualized in different formats and dynamically edited to be adjusted to the available resources, anomalies, dates and other constrains that can arise during daily operation. SUMO shall provide warnings to the users notifying potential conflicts related to the required personal availability or the spare stock for the scheduled tasks. To conclude, SUMO has been designed as a tool to help during the operation management of a scientific facility, and in particular an astronomical observatory. This is done by controlling all operating parameters: personal, assets, spare and supply stocks, tasks and time constrains.

  8. RTEMS CENTRE- Support and Maintenance CENTRE to RTEMS Operating System

    Science.gov (United States)

    Silva, H.; Constantino, A.; Coutunho, M.; Freitas, D.; Faustino, S.; Mota, M.; Colaço, P.; Zulianello, M.

    2008-08-01

    RTEMS stands for Real-Time Operating System for Multiprocessor Systems. It is a full featured Real Time Operating System that supports a variety of open APIs and interface standards. It provides a high performance environment for embedded applications, including a fixed-priority preemptive/non-preemptive scheduler, a comprehensive set of multitasking operations and a large range of supported architectures. Support and maintenance CENTRE to RTEMS operating system (RTEMS CENTRE) is a joint initiative of ESA-Portugal Task force, aiming to build a strong technical competence in the space flight (on- board) software, to offer support, maintenance and improvements to RTEMS. This paper provides a high level description of the current and future activities of the RTEMS CENTRE. It presents a brief description of the RTEMS operating system, a description of the tools developed and distributed to the community [1] and the improvements to be made to the operating system, including facilitation for the qualification of RTEMS (4.8.0) [2] for the space missions.

  9. Investigation of key parameters for the development of reliable ITER baseline operation scenarios using CORSICA

    Science.gov (United States)

    Kim, S. H.; Casper, T. A.; Snipes, J. A.

    2018-05-01

    ITER will demonstrate the feasibility of burning plasma operation by operating DT plasmas in the ELMy H-mode regime with a high ratio of fusion power gain Q ~ 10. 15 MA ITER baseline operation scenario has been studied using CORSICA, focusing on the entry to burn, flat-top burning plasma operation and exit from burn. The burning plasma operation for about 400 s of the current flat-top was achieved in H-mode within the various engineering constraints imposed by the poloidal field coil and power supply systems. The target fusion gain (Q ~ 10) was achievable in the 15 MA ITER baseline operation with a moderate amount of the total auxiliary heating power (~50 MW). It has been observed that the tungsten (W) concentration needs to be maintained low level (n w/n e up to the order of 1.0  ×  10-5) to avoid the radiative collapse and uncontrolled early termination of the discharge. The dynamic evolution of the density can modify the H-mode access unless the applied auxiliary heating power is significantly higher than the H-mode threshold power. Several qualitative sensitivity studies have been performed to provide guidance for further optimizing the plasma operation and performance. Increasing the density profile peaking factor was quite effective in increasing the alpha particle self-heating power and fusion power multiplication factor. Varying the combination of auxiliary heating power has shown that the fusion power multiplication factor can be reduced along with the increase in the total auxiliary heating power. As the 15 MA ITER baseline operation scenario requires full capacity of the coil and power supply systems, the operation window for H-mode access and shape modification was narrow. The updated ITER baseline operation scenarios developed in this work will become a basis for further optimization studies necessary along with the improvement in understanding the burning plasma physics.

  10. Review of Operation and Maintenance Support Systems for Research Reactors

    International Nuclear Information System (INIS)

    Jin, Kyungho; Heo, Gyunyoung; Park, Jaekwan

    2014-01-01

    Operation support systems do not directly control the plant but it can aid decision making itself by obtaining and analyzing large amounts of data. Recently, the demand of research reactor is growing and the need for operation support systems is increasing, but it has not been applied for research reactors. This study analyzes operation and maintenance support systems of NPPs and suggests appropriate systems for research reactors based on analysis. In this paper, operation support systems for research reactors are suggested by comparing with those of power reactors. Currently, research reactors do not cover special systems in order to improve safety and operability in comparison with power reactors. Therefore we expect to improve worth to use by introducing appropriate systems for research reactors. In further research, we will develop an appropriate system such as applications or tools that can be applied to the research reactor

  11. Operation and maintenance of 1MW PUSPATI TRIGA reactor

    International Nuclear Information System (INIS)

    Adnan Bokhari; Mohammad Suhaimi Kassim

    2006-01-01

    The Malaysian Research Reactor, Reactor TRIGA PUSPATI (RTP) has been successfully operated for 22 years for various experiments. Since its commissioning in June 1982 until December 2004, the 1MW pool-type reactor has accumulated more than 21143 hours of operation, corresponding to cumulative thermal energy release of about 14083 MW-hours. The reactor is currently in operation and normally operates on demand, which is normally up to 6 hours a day. Presently the reactor core is made up of standard TRIAGA fuel element consists of 8.5 wt%, 12 wt% and 20 wt% types; 20%-enriched and stainless steel clad. Several measures such as routine preventive maintenance and improving the reactor support systems have been taken toward achieving this long successful operation. Besides normal routine utilization like other TRIGA reactors, new strategies are implemented for effective increase in utilization. (author)

  12. Improvement of nuclear power plant operation and maintenance in Japan

    International Nuclear Information System (INIS)

    Kazushige Hamazaki

    1987-01-01

    Following the inauguration of commercial nuclear power generation in Japan in 1966, capacity factors were held in the relatively low level until around 1975 due to initial-period troubles. With subsequent improvement, however, capacity factors have climbed steadily and recently been sustaining more than 70%. To obtain this successful result, a various kind of improvement have been made not only for the operation management area but also for the maintenance management area in conjunction with the successive effort to reflect the operating experiences to the early stage design. Nowadays nuclear generation has assumed increasing importance for Japan's electrical power needs, and is making a great contribution to stabilizing power supply costs. (author)

  13. Maintenance of electromechanical equipment in quality organization under operating conditions

    International Nuclear Information System (INIS)

    Mercier, J.P.

    1984-01-01

    The paper outlines the principles adopted by the Thermal Production Service of Electricite de France on the basis of the experience of the first years of operation of its 900 MW(e)PWR units for the purpose of improving quality organization in operating conditions in respect of the maintenance of electromechanical safety equipment. This organization is based on application of the usual principles for quality assurance, adapted in accordance with current French regulations. The paper first recalls the now traditional methods of applying the principles of quality organization in the area of equipment maintenance. It then defines particular so-called ''delicate'' activities which, in accordance with the above regulations, are subjected to additional quality organizational procedures; this applies in particular to the area of pre-maintenance preparation and studies and to the control exercised by the French safety authorities over the execution of those activities. The paper explains how the application of the regulations improves maintenance practices compared with standard quality organization. It describes how the attempt to establish a frontier between these two types of activity (current and ''delicate'') has led to the definition of a classification criterion which is technically correct and simple to use and is based on the professional skills of those performing each activity. The paper then describes in greater detail the principal rules for the performance of those tasks which come under the standard organization and those to which more stringent criteria apply. Lastly, it explains the thinking behind equipment surveillance programmes and the analysis of anomalies discovered through surveillance measures or brought to light by operating incidents, the aim of these being to benefit from the experience gained

  14. 40 CFR 63.9600 - What are my operation and maintenance requirements?

    Science.gov (United States)

    2010-07-01

    ... instructions for routine and long-term maintenance. (2) Corrective action procedures for bag leak detection... 40 Protection of Environment 14 2010-07-01 2010-07-01 false What are my operation and maintenance... and Maintenance Requirements § 63.9600 What are my operation and maintenance requirements? (a) As...

  15. Object and operation supported maintenance for mining equipment

    Directory of Open Access Journals (Sweden)

    Walter Bartelmus

    2014-09-01

    Full Text Available The paper aroused in answer to discussion in Mining Magazine (MM September 2011 and July/August 2013. The paper shows that discussion given in the MM issue July/August 2013 does not fulfill expectations expressed in MM issue 2011. The presented paper is the review on maintenance that is based on condition monitoring as tool for detection of faults and failure prevention. Fault and failure are regarded as inevitable during the machine operation as the process of wear and the process of degradation. The question is, if one can influence the wear and degradation process, using condition monitoring. The paper will present technology (in reference to cited papers which demonstrates that the use of the proper method can influence the wear and machine degradation process, using proper condition monitoring techniques and knowing scenarios of wear and degradation process, the maintenance can be rationalized. The presented paper shows possible improvements which are needed to fulfill expectations expressed in MM September 2011 and they are not taken into consideration in MM July/August 3013. These improvements can be fulfilling on the bases of object and operation supported maintenance.

  16. Design and implementation of motion planning of inspection and maintenance robot for ITER-like vessel

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Hesheng; Lai, Yinping [Department of Automation, Shanghai Jiao Tong University, Shanghai 200240 (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Chen, Weidong, E-mail: wdchen@sjtu.edu.cn [Department of Automation, Shanghai Jiao Tong University, Shanghai 200240 (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Cao, Qixin [Institute of Robotics, Shanghai Jiao Tong University, Shanghai 200240 (China)

    2015-12-15

    Robot motion planning is a fundamental problem to ensure the robot executing the task without clashes, fast and accurately in a special environment. In this paper, a motion planning of a 12 DOFs remote handling robot used for inspecting the working state of the ITER-like vessel and maintaining key device components is proposed and implemented. Firstly, the forward and inverse kinematics are given by analytic method. The work space and posture space of this manipulator are both considered. Then the motion planning is divided into three stages: coming out of the cassette mover, moving along the in-vessel center line, and inspecting the D-shape section. Lastly, the result of experiments verified the performance of the motion design method. In addition, the task of unscrewing/screwing the screw demonstrated the feasibility of system in function.

  17. An iterative method for Tikhonov regularization with a general linear regularization operator

    NARCIS (Netherlands)

    Hochstenbach, M.E.; Reichel, L.

    2010-01-01

    Tikhonov regularization is one of the most popular approaches to solve discrete ill-posed problems with error-contaminated data. A regularization operator and a suitable value of a regularization parameter have to be chosen. This paper describes an iterative method, based on Golub-Kahan

  18. New Operation and Maintenance Contract for Electrical Network

    CERN Document Server

    Kowalik, G

    2001-01-01

    The Electrical Exploitation is one of the few remaining operation services at CERN which nearly entirely relies on the CERN staff. Last year CERN policy, in connection with the LHC project needs, have led to the formulation of the strategy of out-sourcing of the Electrical Exploitation activities, market survey and subsequent Invitation to Tender. The following paper presents the approach used in the preparation of the Invitation to Tender and in solving of the out-sourcing issues applied to the operation and maintenance of the CERN electrical network. In particular the problems of the results oriented contract, quality assurance and performance as well requirement of the constantly increasing productivity of the Contractors team are treated. The paper gives also the particularities of the application of the out-sourcing to the electrical operation service as will as techniques used for the estimation of the work load of the activities being outsourced.

  19. DOE-EM-45 Packaging Operations And Maintenance Course

    International Nuclear Information System (INIS)

    Watkins, R.; England, J.

    2010-01-01

    Savannah River National Laboratory - Savannah River Packaging Technology (SRNL-SRPT) delivered the inaugural offering of the Packaging Operations and Maintenance Course for DOE-EM-45's Packaging Certification Program (PCP) at the University of South Carolina Aiken on September 1 and 2, 2009. Twenty-nine students registered, attended, and completed this training. The DOE-EM-45 Packaging Certification Program (PCP) sponsored the presentation of a new training course, Packaging Maintenance and Operations, on September 1-2, 2009 at the University of South Carolina Aiken (USC-Aiken) campus in Aiken, SC. The premier offering of the course was developed and presented by the Savannah River National Laboratory, and attended by twenty-nine students across the DOE, NNSA and private industry. This training informed package users of the requirements associated with handling shipping containers at a facility (user) level and provided a basic overview of the requirements typically outlined in Safety Analysis Report for Packaging (SARP) Chapters 1, 7, and 8. The course taught packaging personnel about the regulatory nature of SARPs to help reduce associated and often costly packaging errors. Some of the topics covered were package contents, loading, unloading, storage, torque requirements, maintaining records, how to handle abnormal conditions, lessons learned, leakage testing (including demonstration), and replacement parts. The target audience for this course was facility operations personnel, facility maintenance personnel, and field quality assurance personnel who are directly involved in the handling of shipping containers. The training also aimed at writers of SARP Chapters 1, 7, and 8, package designers, and anyone else involved in radioactive material packaging and transportation safety. Student feedback and critiques of the training were very positive. SRNL will offer the course again at USC Aiken in September 2010.

  20. How the Station will operate. [operation, management, and maintenance in space

    Science.gov (United States)

    Cox, John T.

    1988-01-01

    Aspects of the upcoming operational phase of the Space Station (SS) are examined. What the crew members will do with their time in their specialized roles is addressed. SS maintenance and servicing and the interaction of the SS Control Center with Johnson Space Center is discussed. The planning of payload operations and strategic planning for the SS are examined.

  1. Toward autonomous operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, M.

    1994-01-01

    Issues toward realization of autonomous operation as well as maintenance of nuclear power plants are reviewed in this paper. First, the necessity and significance of the technical program aiming at the establishment of autonomous nuclear plant are discussed through reviewing the history and current status computerized operation of complex artifacts. Then, key technologies currently studied to meet the need within the framework of artificial intelligence (AI) and advanced robotics are described. Among such AI-technologies are distributed multi-agent system, operator thinking model, and advanced man-machine interface design. Advances in robot technology attained include active sensing technique and multi-unit autonomous maintenance robot systems. Techniques for simulation of human action have been pursued as basic issues for understanding mechanisms behind human behavior. In addition to the individual developments, methodological topics relevant to the autonomy of nuclear facilities are briefly addressed. The concepts called methodology diversity and dynamic functionality restoration (realization) are introduced and discussed as the underlining principles to be considered in the development of the autonomous nuclear power plants. (author)

  2. Hypertext-based integration for nuclear plant maintenance and operations

    International Nuclear Information System (INIS)

    Tsoukalas, L.H.; Upadhyaya, B.R.

    1991-01-01

    A methodology is presented that uses fuzzy graphs in the emerging paradigm of hypertext for the purpose of integrating data, information and multifaceted knowledge resources abounding in power plant operations and maintenance. A hypertext system is viewed as a set of nodes and links where with each link we associate membership functions embodying context-dependent criteria for navigating large information spaces. A general framework for navigation is outlined and graph-theory navigational tools are developed. A numerical example and a HyperCard-based prototype for monitoring special material in the MHTGR-NPR are included. 10 refs., 12 figs

  3. Operation and maintenance experience at the TRIGA Mainz reactor

    International Nuclear Information System (INIS)

    Menke, Helmut

    1976-01-01

    Oscillations observed in the linear power channel especially at low steady state power with the pulse-rod in down position were found to be due to wear of connections of the pulse-rod. The downstream water from the cooling system caused a swing of the rod, which in turn induced the power oscillations. The wear can be regarded as normal, as more than 10,000 pulses have been performed so far. The repairs of the rod assembly are described. No major problems in operation and maintenance of the TRIGA Mainz were met since 1974. Results of routine inspections as fuel element measurements, power calibrations, etc., are described and discussed. (author)

  4. 25 CFR 39.1203 - Future consideration of contract school operation and maintenance funding.

    Science.gov (United States)

    2010-04-01

    ... EDUCATION THE INDIAN SCHOOL EQUALIZATION PROGRAM Contract School Operation and Maintenance Fund § 39.1203 Future consideration of contract school operation and maintenance funding. The Assistant Secretary shall arrange for full funding for operation and maintenance of contract schools by fiscal year 1981. ...

  5. Transient heat loads in current fusion experiments, extrapolation to ITER and consequences for its operation

    International Nuclear Information System (INIS)

    Loarte, A; Saibene, G; Sartori, R; Riccardo, V; Andrew, P; Paley, J; Fundamenski, W; Eich, T; Herrmann, A; Pautasso, G; Kirk, A; Counsell, G; Federici, G; Strohmayer, G; Whyte, D; Leonard, A; Pitts, R A; Landman, I; Bazylev, B; Pestchanyi, S

    2007-01-01

    New experimental results on transient loads during ELMs and disruptions in present divertor tokamaks are described and used to carry out a extrapolation to ITER reference conditions and to draw consequences for its operation. In particular, the achievement of low energy/convective type I edge localized modes (ELMs) in ITER-like plasma conditions seems the only way to obtain transient loads which may be compatible with an acceptable erosion lifetime of plasma facing components (PFCs) in ITER. Power loads during disruptions, on the contrary, seem to lead in most cases to an acceptable divertor lifetime because of the relatively small plasma thermal energy remaining at the thermal quench and the large broadening of the power flux footprint during this phase. These conclusions are reinforced by calculations of the expected erosion lifetime, under these load conditions, which take into account a realistic temporal dependence of the power fluxes on PFCs during ELMs and disruptions

  6. Confinement margins for ignition and driven operation in Iter Eda ID

    International Nuclear Information System (INIS)

    Johner, J.

    1995-09-01

    Preliminary calculations for ITER EDA ID have been performed using the 1/2D thermal equilibrium code HELIOS. It is found that: - The maximum ignition margin for ITER ID (29%) is 6% less than for ITER OD (35%) and 5% less than for ITER CDA (34%). - Decreasing the ration τ * He /τ E from the nominal value 10 to a value of 5 gives a 12% gain in the maximum ignition margin. Increasing the ration from 10 to 15 causes a 22% loss in the margin. Furthermore, ignited equilibria non longer exist for τ * He /τ E ≥ 17.6. - Operation in driven mode with 50 MW of external power increases the confinement capability by 13%. With 100 MW, the improvement is 24%. - Lowering the fusion power from 1500 to 1000 MW slightly improves the maximum ignition margin (+5%) and allows operation below the Greenwald density limit. - A 10% reduction of the toroidal magnetic field with a correlative diminution of the plasma current for constant safety factor operation, causes a dramatic reduction (-18%) of the maximum ignition margin. - A fraction of neon of 0.68% would completely suppress the ignition margin. Furthermore, ignited equilibria, with the nominal fusion power and τ * He /τ E , no longer exist when the neon fraction exceeds 0.75%. (Author). 2 refs., 10 figs

  7. Heating and current drive requirements towards steady state operation in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Poli, F. M.; Kessel, C. E.; Gorelenkova, M. [Princeton Plasma Physics Laboratory, Princeton, NJ 08543 (United States); Bonoli, P. T. [MIT Plasma Science and Fusion Center, Cambridge, MA 02139 (United States); Batchelor, D. B. [Oak Ridge National Laboratory, Oak Ridge, TN 37831-6169 (United States); Harvey, B.; Petrov, Y. [CompX, Box 2672, Del Mar, CA 92014 (United States)

    2014-02-12

    Steady state scenarios envisaged for ITER aim at optimizing the bootstrap current, while maintaining sufficient confinement and stability to provide the necessary fusion yield. Non-inductive scenarios will need to operate with Internal Transport Barriers (ITBs) in order to reach adequate fusion gain at typical currents of 9 MA. However, the large pressure gradients associated with ITBs in regions of weak or negative magnetic shear can be conducive to ideal MHD instabilities, reducing the no-wall limit. The E × B flow shear from toroidal plasma rotation is expected to be low in ITER, with a major role in the ITB dynamics being played by magnetic geometry. Combinations of H/CD sources that maintain weakly reversed magnetic shear profiles throughout the discharge are the focus of this work. Time-dependent transport simulations indicate that, with a trade-off of the EC equatorial and upper launcher, the formation and sustainment of quasi-steady state ITBs could be demonstrated in ITER with the baseline heating configuration. However, with proper constraints from peeling-ballooning theory on the pedestal width and height, the fusion gain and the maximum non-inductive current are below the ITER target. Upgrades of the heating and current drive system in ITER, like the use of Lower Hybrid current drive, could overcome these limitations, sustaining higher non-inductive current and confinement, more expanded ITBs which are ideal MHD stable.

  8. Heating and current drive requirements towards steady state operation in ITER

    Science.gov (United States)

    Poli, F. M.; Bonoli, P. T.; Kessel, C. E.; Batchelor, D. B.; Gorelenkova, M.; Harvey, B.; Petrov, Y.

    2014-02-01

    Steady state scenarios envisaged for ITER aim at optimizing the bootstrap current, while maintaining sufficient confinement and stability to provide the necessary fusion yield. Non-inductive scenarios will need to operate with Internal Transport Barriers (ITBs) in order to reach adequate fusion gain at typical currents of 9 MA. However, the large pressure gradients associated with ITBs in regions of weak or negative magnetic shear can be conducive to ideal MHD instabilities, reducing the no-wall limit. The E × B flow shear from toroidal plasma rotation is expected to be low in ITER, with a major role in the ITB dynamics being played by magnetic geometry. Combinations of H/CD sources that maintain weakly reversed magnetic shear profiles throughout the discharge are the focus of this work. Time-dependent transport simulations indicate that, with a trade-off of the EC equatorial and upper launcher, the formation and sustainment of quasi-steady state ITBs could be demonstrated in ITER with the baseline heating configuration. However, with proper constraints from peeling-ballooning theory on the pedestal width and height, the fusion gain and the maximum non-inductive current are below the ITER target. Upgrades of the heating and current drive system in ITER, like the use of Lower Hybrid current drive, could overcome these limitations, sustaining higher non-inductive current and confinement, more expanded ITBs which are ideal MHD stable.

  9. Reactor technology: power conversion systems and reactor operation and maintenance

    International Nuclear Information System (INIS)

    Powell, J.R.

    1977-01-01

    The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

  10. Feasibility study for a transportation operations system cask maintenance facility

    Energy Technology Data Exchange (ETDEWEB)

    Rennich, M.J.; Medley, L.G.; Attaway, C.R.

    1991-01-01

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

  11. Hydraulic screw fastening devices - design, maintenance, operational experience

    International Nuclear Information System (INIS)

    Lachner.

    1976-01-01

    With hydraulic screw fastening devices, pretension values with a maximum deviation of +-2.5% from the rated value can be achieved. This high degree of pretension accuracy is of considerable importance with regard to the safety factor required for the screw connection between reactor vessel head and reactor vessel. The operating rhythm of a nuclear power station with its refuelling art regular intervals makes further demands on the screw fastening device, in particular in connection with the transport of screws and for nuts. The necessary installations extend the screw fastening device into a combination of a high-pressure hydraulic cylinder system with an electrical or pneumoelectrical driving unit and an electrical control unit. Maintenance work is complicated by the large number of identical, highly stressed structural elements in connection with an unfavourable relation operating time/outage time. The problems have been perpetually reduced by close cooperation between the manufacturers and users of screw fastening devices. (orig./AK) [de

  12. Feasibility study for a transportation operations system cask maintenance facility

    International Nuclear Information System (INIS)

    Rennich, M.J.; Medley, L.G.; Attaway, C.R.

    1991-01-01

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs

  13. Operation and Maintenance Plan for the 300-FF-5 Operable Unit

    International Nuclear Information System (INIS)

    Singleton, K.M.

    1996-09-01

    This document is the operation and maintenance plan for the 300-FF-5 groundwater operable unit. The purpose of this plan is to identify tasks necessary to verify the effectiveness of the selected alternative. This plan also describes the monitoring program and administrative tasks that will be used as the preferred alternative for the remediation of groundwater in the 300-FF-5 Operable Unit. The preferred alternative selected for remediation of groundwater consists of institutional controls

  14. Embracing Safe Ground Test Facility Operations and Maintenance

    Science.gov (United States)

    Dunn, Steven C.; Green, Donald R.

    2010-01-01

    Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

  15. Lessons learned from operating experience, maintenance procedures and training measures

    International Nuclear Information System (INIS)

    Guttner, K.; Gronau, D.

    2003-01-01

    Training programmes for nuclear facility personnel as a result of the developing phase of SAT have to be approved in the subsequent implementation and evaluation phases with the consequence of several feedback activities in the whole training process. The effectiveness of this procedure has to be evaluated especially with respect to an improvement of safety culture, shorter outage times or better plant performance, resulting in a smaller number of incidents due to human failures. The first two arguments are directly connected with all types of maintenance work in a nuclear power plant and the related preparatory training measures. The reduction of incidents due to human failures is the result of different influences, i.e. training of the operational as well as of the maintenance personnel together with changes of the operating procedures or system design. Though an evaluation of the training process should always be based on a clear definition of criteria by which the fulfilment of the learning objectives can be measured directly, the real effectiveness of training is proven by the behaviour and attitude of the personnel which can only be taken from indirect indicators. This is discussed in more detail for some examples being partly related to the above mentioned arguments. An excellent plant performance, representing a general objective of all activities, can be analysed by the changed number and reasons of incidents in a plant during its operation time. Two further examples are taken from the reactor service field where there is a tendency to reduce the individual dose rates by changed devices and/or procedures as an output from training experience with mockups. Finally the rationalisation of refresher training for operational personnel by the use of interactive teaching programs (Computer Based Training - CBT) is presented which integrate learning objectives together with a test module. (author)

  16. ITER...ation

    International Nuclear Information System (INIS)

    Troyon, F.

    1997-01-01

    Recurrent attacks against ITER, the new generation of tokamak are a mix of political and scientific arguments. This short article draws a historical review of the European fusion program. This program has allowed to build and manage several installations in the aim of getting experimental results necessary to lead the program forwards. ITER will bring together a fusion reactor core with technologies such as materials, superconductive coils, heating devices and instrumentation in order to validate and delimit the operating range. ITER will be a logical and decisive step towards the use of controlled fusion. (A.C.)

  17. RA reactor operation and maintenance in 1994, Part 1

    International Nuclear Information System (INIS)

    Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Mikic, N.; Tanaskovic, M.

    1994-01-01

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. The spent fuel elements used from the very beginning of reactor operation are stored in the existing pools. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988 and was fulfilled in 1990. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor [sr

  18. Experiences on operation, maintenance and utilization in JRR-2

    International Nuclear Information System (INIS)

    1994-08-01

    The Japan Research Reactor No.2 (JRR-2) is a high performance 10 MW multi purpose research reactor, heavy water moderated and cooled enriched uranium fuel used. Since the first criticality was attained in October, 1960, JRR-2 has been operated to satisfy the utilization demands, such as irradiation of fuel and materials, neutron beam experiments, radio isotope production and B.N.C.T (Boron Neutron Capture Therapy). During the operation, various kinds of troubles mainly caused by the old design concept had been occurred at the JRR-2 systems and components. Those troubles were solved with adequate countermeasures of timely repairs and large scale modifications with newest techniques. The works above were completely carried out by the staff of JRR-2 and related divisions. As a result, JRR-2 became one of the oldest research reactors which are still under operation in the world. Since JRR-2 has been utilized for more than 30 years, the operation mode was changed from 12 days-one cycle to 3 days-one cycle in April, 1994, taking into consideration aging of the reactor systems. In this paper, the experiences of JRR-2 for more than 30 years such as operation, maintenance, repair, modifications and utilization on JRR-2 are described. (author)

  19. Research nuclear reactor RA - Annual Report 1975. Operation and maintenance

    International Nuclear Information System (INIS)

    Martinc, R.

    1976-01-01

    The plan for 1975 was successfully fulfilled. This is reflected in research related to improvement of operating properties of the RA reactor, mostly due to the effort of the RA staff employed in operation and maintenance of the reactor. Fuel saving achieved by this activity amounted to about 38% (80% enriched fuel). Preliminary work is done, concerned with new reactor core with highly enriched fuel. This is a significant saving as well. New fuel elements have arrived at the end of this year. It is going to enable increase of neutron flux by 50% without changing the nominal operating power. The possibility of further improvement of the reactor are analyzed, to enable material testing and production of radioactive sources. Mid term plan for reactor operation was made according to this analysis. It is planned to further increase the neutron flux in isolated smaller zones, and building new experimental loops with cooling and fast neutron converters. Much was done to increase the safety level of reactor operation and preparing the safety report [sr

  20. Primary design and operation analysis of the ITER air transfer system

    International Nuclear Information System (INIS)

    Wang Haitian; Li Ge; Qin Shijun

    2010-01-01

    Air transfer system (ATS) is a remote handling transfer, which can work in the nuclear radiation environment and can be driven by the electricity fully. Its motion power is provided by several servo motors. The remote control technology of ATS, which is China taking part in the plan of international Tokamak experimental reactor (ITER) and grasping this technology, is one of key technologies of ITER. The remote handling technology can lay the foundation for developing demonstration nuclear fusion power plant in China on self-reliance. Because there is gamma irradiation and hazard material in these ITER parts, all required maintenance of port plugs and inner components are been transmitted by ATS. The pick-up or drop-off these components are completed by means of a remotely controlled TCS system between the Vacuum Vessel and the Hot Cell through the bridge-gallery. Tokamak building includes three floors, including upper port, equatorial port and lower port, linked by a lift. According to each port level configuration and safety requirement, the radius of curvature with ATS trajectory is optimized, and a trajectory of each level is determined by positioned guidance beacons. At last, the results of computer aided design (CAD) show single trajectory guidance of ATS in each level is available. (authors)

  1. Operation and Maintenance of Water Pollution Control Facilities: A WPCF White Paper.

    Science.gov (United States)

    Hill, William R.; And Others

    1979-01-01

    Presented are the recommendations of the Water Pollution Control Federation for operation and maintenance consideration during the planning design, construction, and operation of wastewater treatment facilities. (CS)

  2. External heating and current drive source requirements towards steady-state operation in ITER

    Science.gov (United States)

    Poli, F. M.; Kessel, C. E.; Bonoli, P. T.; Batchelor, D. B.; Harvey, R. W.; Snyder, P. B.

    2014-07-01

    Steady state scenarios envisaged for ITER aim at optimizing the bootstrap current, while maintaining sufficient confinement and stability to provide the necessary fusion yield. Non-inductive scenarios will need to operate with internal transport barriers (ITBs) in order to reach adequate fusion gain at typical currents of 9 MA. However, the large pressure gradients associated with ITBs in regions of weak or negative magnetic shear can be conducive to ideal MHD instabilities, reducing the no-wall limit. The E × B flow shear from toroidal plasma rotation is expected to be low in ITER, with a major role in the ITB dynamics being played by magnetic geometry. Combinations of heating and current drive (H/CD) sources that sustain reversed magnetic shear profiles throughout the discharge are the focus of this work. Time-dependent transport simulations indicate that a combination of electron cyclotron (EC) and lower hybrid (LH) waves is a promising route towards steady state operation in ITER. The LH forms and sustains expanded barriers and the EC deposition at mid-radius freezes the bootstrap current profile stabilizing the barrier and leading to confinement levels 50% higher than typical H-mode energy confinement times. Using LH spectra with spectrum centred on parallel refractive index of 1.75-1.85, the performance of these plasma scenarios is close to the ITER target of 9 MA non-inductive current, global confinement gain H98 = 1.6 and fusion gain Q = 5.

  3. Quality control in the design, fabrication and operation of the ITER magnets

    International Nuclear Information System (INIS)

    Mitchell, N.

    2006-01-01

    The ITER magnets are a complex system involving interfaces between many advanced technologies (superconductors, forging/welding/machining of massive structures, cryogenics, composites and moulding, high voltage electrical), yet at the same time form part of the ITER 'basic machine' which is required to operate at the design parameters, broadly failure free, for the design life of the tokamak. This imposes special quality control problems for the ITER project integration by the ITER International Team (IT) through the design, fabrication and operation. The magnets are not a test bed for new technology but in spite of this must use it, successfully. There is little previous experience of such a system but full functionality is required from the start, with limited opportunity for adjustment. And, finally, costs and schedule must be contained. The procurement strategy for the machine, with magnet components being supplied 'in kind', requires particular attention to the specifications, scheduling and quality control (QC). Special issues here are the testing requirements on magnet components, especially before final installation but also at critical intermediate stages. Unnecessary or ineffective quality control procedures cause delay and high costs, and divert attention from critical items. The main points of the magnet QC programme are summarised, including the use of codes and standards, qualification, manufacturing quality assurance, commissioning and in-service inspection

  4. RTEMS Centre - Support and Maintenance Centre to RTEMS Operating System

    Science.gov (United States)

    Silva, H.; Constantino, A.; Freitas, D.; Coutinho, M.; Faustino, S.; Mota, M.; Colaço, P.; Sousa, J.; Dias, L.; Damjanovic, B.; Zulianello, M.; Rufino, J.

    2009-05-01

    RTEMS CENTRE - Support and Maintenance Centre to RTEMS Operating System is a joint ESA/Portuguese Task Force initiative to develop a support and maintenance centre to the Real-Time Executive for Multiprocessor Systems (RTEMS). This paper gives a high level visibility of the progress, the results obtained and the future work in the RTEMS CENTRE [6] and in the RTEMS Improvement [7] projects. RTEMS CENTRE started officially in November 2006, with the RTEMS 4.6.99.2 version. A full analysis of RTEMS operating system was produced. The architecture was analysed in terms of conceptual, organizational and operational concepts. The original objectives [1] of the centre were primarily to create and maintain technical expertise and competences in this RTOS, to develop a website to provide the European Space Community an entry point for obtaining support (http://rtemscentre.edisoft.pt), to design, develop, maintain and integrate some RTEMS support tools (Timeline Tool, Configuration and Management Tools), to maintain flight libraries and Board Support Packages, to develop a strong relationship with the World RTEMS Community and finally to produce some considerations in ARINC-653, DO-178B and ECSS E-40 standards. RTEMS Improvement is the continuation of the RTEMS CENTRE. Currently the RTEMS, version 4.8.0, is being facilitated for a future qualification. In this work, the validation material is being produced following the Galileo Software Standards Development Assurance Level B [5]. RTEMS is being completely tested, errors analysed, dead and deactivated code removed and tests produced to achieve 100% statement and decision coverage of source code [2]. The SW to exploit the LEON Memory Management Unit (MMU) hardware will be also added. A brief description of the expected implementations will be given.

  5. Inertial Fusion Power Plant Concept of Operations and Maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Anklam, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Knutson, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dunne, A. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kasper, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sheehan, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lang, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Roberts, V. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mau, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-01-15

    Parsons and LLNL scientists and engineers performed design and engineering work for power plant pre-conceptual designs based on the anticipated laser fusion demonstrations at the National Ignition Facility (NIF). Work included identifying concepts of operations and maintenance (O&M) and associated requirements relevant to fusion power plant systems analysis. A laser fusion power plant would incorporate a large process and power conversion facility with a laser system and fusion engine serving as the heat source, based in part on some of the systems and technologies advanced at NIF. Process operations would be similar in scope to those used in chemical, oil refinery, and nuclear waste processing facilities, while power conversion operations would be similar to those used in commercial thermal power plants. While some aspects of the tritium fuel cycle can be based on existing technologies, many aspects of a laser fusion power plant presents several important and unique O&M requirements that demand new solutions. For example, onsite recovery of tritium; unique remote material handling systems for use in areas with high radiation, radioactive materials, or high temperatures; a five-year fusion engine target chamber replacement cycle with other annual and multi-year cycles anticipated for major maintenance of other systems, structures, and components (SSC); and unique SSC for fusion target waste recycling streams. This paper describes fusion power plant O&M concepts and requirements, how O&M requirements could be met in design, and how basic organizational and planning issues can be addressed for a safe, reliable, economic, and feasible fusion power plant.

  6. Technological exploitation of Deuterium–Tritium operations at JET in support of ITER design, operation and safety

    Energy Technology Data Exchange (ETDEWEB)

    Batistoni, P., E-mail: paola.batistoni@enea.it [ENEA, Dipartimento Fusione e Sicurezza Nucleare, Via E. Fermi 45, 00044 Frascati, Roma (Italy); Campling, D. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Conroy, S. [Department of Physics and Astronomy, Uppsala University, SE-75120 Uppsala (Sweden); Croft, D. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Giegerich, T. [Karlsruhe Institute of Technology, P.O.Box 3640, D-76021 Karlsruhe (Germany); Huddleston, T.; Lefebvre, X. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Lengar, I. [Jozef Stefan Institute, Reactor Physics Department, Jamova 39, SI-1000 Ljubljana (Slovenia); Lilley, S. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Peacock, A. [JET Exploitation Unit, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Pillon, M. [ENEA, Dipartimento Fusione e Sicurezza Nucleare, Via E. Fermi 45, 00044 Frascati, Roma (Italy); Popovichev, S.; Reynolds, S. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Vila, R. [Laboratorio Nacional de Fusión, CIEMAT, Madrid (Spain); Villari, R. [ENEA, Dipartimento Fusione e Sicurezza Nucleare, Via E. Fermi 45, 00044 Frascati, Roma (Italy); Bekris, N. [ITER Physics Department, EUROfusion Consortium, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom)

    2016-11-01

    Highlights: • Within the framework of the EUROfusion programme, a work-package of technology projects (WPJET3) is being carried out in conjunction with the planned Deuterium–Tritium experiment on JET (DTE2). • The objective is to maximise the scientific and technological return of DT operations at JET in support of ITER. • Preparatory experiments, analyses and studies are carried out in several fusion nuclear technology areas. • These are: neutronics, neutron induced activation and damage in ITER materials, nuclear safety, tritium retention, permeation and outgassing, and waste production. • This paper presents the progress since the start of the project in 2014. - Abstract: Within the framework of the EUROfusion programme, a work-package of technology projects (WPJET3) is being carried out in conjunction with the planned Deuterium–Tritium experiment on JET (DTE2) with the objective of maximising the scientific and technological return of DT operations at JET in support of ITER. This paper presents the progress since the start of the project in 2014 in the preparatory experiments, analyses and studies in the areas of neutronics, neutron induced activation and damage in ITER materials, nuclear safety, tritium retention, permeation and outgassing, and waste production in preparation of DTE2.

  7. Marginal costs for road maintenance and operation - a cost function approach

    OpenAIRE

    Haraldsson, Mattias

    2007-01-01

    Using observational data covering the whole Swedish national road network for the period 1998-2002, this paper estimates a set of maintenance and operation cost functions. It is found that costs for all operation and maintenance measures increase with traffic intensity, with two exceptions; total operation and winter operation measures are fixed cost activities. All other operation and maintenance measures have short run elasticities in the range 0.25-0.60. The impact of an additional vehicle...

  8. Integration of plant life management in operation and maintenance

    International Nuclear Information System (INIS)

    Hutin, Jean-Pierre

    2002-01-01

    Full text: 1 - INTRODUCTION. Electricite de France is now operating 58 PWR nuclear power plants which produce 75% of french electricity. Besides maintaining safety and availability on a routine basis, it is outmost important to protect the investment. Indeed, such an asset is a tremendous advantage just as the company is going to face the new european electricity market. That is the reason why EDF is devoting important effort to implement ageing management as an integral part of operation and maintenance programs. But it must be recognized that NPP lifetime is not threatened only by component-related problems: other less technical issues must be seriously considered like industrial support, information system, skilled people, public acceptance, etc. 2 - LIFE MANAGEMENT POLICY. In France, there is no limited licensing period for NPPs. The life management policy of nuclear power plants is based on three principles: - safe and cost-effective operation, looking for excellence in daily activities, with an effective experience feedback organisation taking advantage of the high level of standardization of the units, - every ten years, a new set of safety standards, a complete review of each facility and an upgrading of its safety level through appropriate modifications while maintaining unit standardization in all the fleet, - a Life Management Program, at corporate level, which permanently scrutinizes operation and maintenance activities to identify decisions which could impair plant lifetime and which surveys research and development programs related to ageing phenomenon understanding. 3 - INTEGRATION OF LIFETIME CONCERN IN O and M ACTIVITIES. It is outmost important to take in account lifetime concern in daily operation and maintenance activities and this must be done as early as possible in plant life. Even though sophisticated assessments require engineering capacity, many good ideas may arise from plant staff. For that reason, increasing lifetime awareness of plant

  9. Operations & Maintenance Best Practices - A Guide to Achieving Operational Efficiency Release 3.0

    Energy Technology Data Exchange (ETDEWEB)

    None

    2010-08-01

    This Operations and Maintenance (O&M) Best Practices Guide was developed under the direction of the U.S. Department of Energy’s Federal Energy Management Program (FEMP). The mission of FEMP is to facilitate the Federal Government’s implementation of sound, cost effective energy management and investment practices to enhance the nation’s energy security and environmental stewardship.

  10. Installation, Operation, and Operator's Maintenance of Diesel-Engine-Driven Generator Sets.

    Science.gov (United States)

    Marine Corps Inst., Washington, DC.

    This student guide, one of a series of correspondence training courses designed to improve the job performance of members of the Marine Corps, contains three study units dealing with the skills needed by individuals responsible for the installation, operation, and maintenance of diesel engine-driven generator sets. The first two units cover…

  11. Development the conceptual design of Knowledge Based System for Integrated Maintenance Strategy and Operation

    Science.gov (United States)

    Milana; Khan, M. K.; Munive, J. E.

    2014-07-01

    The importance of maintenance has escalated significantly by the increasing of automation in manufacturing process. This condition switches traditional maintenance perspective of inevitable cost into the business competitive driver. Consequently, maintenance strategy and operation decision needs to be synchronized to business and manufacturing concerns. This paper shows the development of conceptual design of Knowledge Based System for Integrated Maintenance Strategy and Operation (KBIMSO). The framework of KBIMSO is elaborated to show the process of how the KBIMSO works to reach the maintenance decision. By considering the multi-criteria of maintenance decision making, the KB system embedded with GAP and AHP to support integrated maintenance strategy and operation which is novel in this area. The KBIMSO is useful to review the existing maintenance system and give reasonable recommendation of maintenance decisions in respect to business and manufacturing perspective.

  12. Development the conceptual design of Knowledge Based System for Integrated Maintenance Strategy and Operation

    International Nuclear Information System (INIS)

    Milana; Khan, M K; Munive, J E

    2014-01-01

    The importance of maintenance has escalated significantly by the increasing of automation in manufacturing process. This condition switches traditional maintenance perspective of inevitable cost into the business competitive driver. Consequently, maintenance strategy and operation decision needs to be synchronized to business and manufacturing concerns. This paper shows the development of conceptual design of Knowledge Based System for Integrated Maintenance Strategy and Operation (KBIMSO). The framework of KBIMSO is elaborated to show the process of how the KBIMSO works to reach the maintenance decision. By considering the multi-criteria of maintenance decision making, the KB system embedded with GAP and AHP to support integrated maintenance strategy and operation which is novel in this area. The KBIMSO is useful to review the existing maintenance system and give reasonable recommendation of maintenance decisions in respect to business and manufacturing perspective

  13. Helium experiments on Alcator C-Mod in support of ITER early operations

    Science.gov (United States)

    Kessel, C. E.; Wolfe, S. M.; Reinke, M. L.; Hughes, J. W.; Lin, Y.; Wukitch, S. J.; Baek, S. G.; Bonoli, P. T.; Chilenski, M.; Diallo, A.; the Alcator C-Mod Team

    2018-05-01

    Helium majority experiments on Alcator C-Mod were performed to compare with deuterium discharges, and inform ITER early operations. ELMy H-modes were produced with a special plasma shape at B T  =  5.3 T, I P  =  0.9 MA, at q 95 ~ 3.8. The He fraction ranged over, n He,L/n L  =  0.2-0.4, with n D,L/n L  =  0.15-0.26, compared to D plasmas with n D,L/n L  =  0.85-0.97. The power to enter the H-mode in He was found to be greater than ~2 times that for D discharges, in the low density region  operation in ITER.

  14. Budgeting for Solar PV Plant Operations & Maintenance: Practices and Pricing.

    Energy Technology Data Exchange (ETDEWEB)

    Enbar, Nadav [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Weng, Dean [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Klise, Geoffrey Taylor [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    With rising grid interconnections of solar photovoltaic (PV) systems, greater attention is being trained on lifecycle performance, reliability, and project economics. Expected to meet production thresholds over a 20-30 year timeframe, PV plants require a steady diet of operations and maintenance (O&M) oversight to meet contractual terms. However, industry best practices are only just beginning to emerge, and O&M budgets—given the arrangement of the solar project value chain—appear to vary widely. Based on insights from in-depth interviews and survey research, this paper presents an overview of the utility-scale PV O&M budgeting process along with guiding rationales, before detailing perspectives on current plant upkeep activities and price points largely in the U.S. It concludes by pondering potential opportunities for improving upon existing O&M budgeting approaches in ways that can benefit the industry at-large.

  15. Budgeting for Solar PV Plant Operations & Maintenance: Practices and Pricing.

    Energy Technology Data Exchange (ETDEWEB)

    Enbar, Nadav [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Weng, Dean [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Klise, Geoffrey Taylor [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    With rising grid interconnections of solar photovoltaic (PV) systems, greater attention is being trained on lifecycle performance, reliability, and project economics. Expected to meet production thresholds over a 20-30 year timeframe, PV plants require a steady diet of operations and maintenance (O&M) oversight to meet contractual terms. However, industry best practices are only just beginning to emerge, and O&M budgets—given the arrangement of the solar project value chain—appear to vary widely. Based on insights from in-depth interviews and survey research, this paper presents an overview of the utility-scale PV O&M budgeting process along with guiding rationales, before detailing perspectives on current plant upkeep activities and price points largely in the U.S. It concludes by pondering potential opportunities for improving upon existing O&M budgeting approaches in ways that can benefi t the industry at-large.

  16. Wave Front Sets with respect to the Iterates of an Operator with Constant Coefficients

    Directory of Open Access Journals (Sweden)

    C. Boiti

    2014-01-01

    Full Text Available We introduce the wave front set WF*P(u with respect to the iterates of a hypoelliptic linear partial differential operator with constant coefficients of a classical distribution u∈′(Ω in an open set Ω in the setting of ultradifferentiable classes of Braun, Meise, and Taylor. We state a version of the microlocal regularity theorem of Hörmander for this new type of wave front set and give some examples and applications of the former result.

  17. Human Resources Training Requirement on NPP Operation and Maintenance

    International Nuclear Information System (INIS)

    Nurlaila; Yuliastuti

    2009-01-01

    This paper discussed the human resources requirement on Nuclear Power Plant (NPP) operation and maintenance (O&M) phase related with the training required for O&M personnel. In addition, this paper also briefly discussed the availability of training facilities domestically include with some suggestion to develop the training facilities intended for the near future time in Indonesia. This paper was developed under the assumptions that Indonesia will build twin unit of NPP with capacity 1000 MWe for each using the turnkey contract method. The total of NPP O&M personnel were predicted about 692 peoples which consists of 42 personnel located in the head quarter and the rest 650 people work at NPP site. Up until now, Indonesia had the experience on operating and maintaining the nonnuclear power plant and several research reactors namely Kartini Reactor Yogyakarta, Triga Mark II Reactor Bandung, and GA Siwabessy Reactor Serpong. Beside that, experience on operating and maintaining the NPP in other countries would act as one of the reference to Indonesia in formulating an appropriate strategy to develop NPP human resources particularly in O&M phases. Education and training development program could be done trough the cooperation with vendor candidates. (author)

  18. EN-CV during LS1: upgrade, consolidation, maintenance, operation

    International Nuclear Information System (INIS)

    Nonis, M.

    2012-01-01

    The Cooling and Ventilation (CV) Group in the Engineering Department (EN) will be heavily involved in several projects and activities during the long shutdown in 2013 and 2014 (LS1) within a time-frame limited to around twelve months. According to the requests received so far, most projects are related to the upgrade of users' equipment, consolidation work, and the construction of new plants. However, through the experience gained from the first years of the LHC run, some projects are also needed to adapt the existing installations to the new operating parameters. Some of these projects are presented hereafter, outlining the impact that they will have on operational working conditions or risks of breakdown. Among these projects we find: the PM32 raising pumps, the cooling of the CERN Control Center, R2E, the backup cooling towers for ATLAS and cryogenics, a thermosyphon for ATLAS, or new pumps in UWs. Finally, EN-CV activities during LS1 for maintenance, operation, and commissioning will be mentioned since they represent a major workload for the Group

  19. RA reactor operation and maintenance in 1996, Part 1

    International Nuclear Information System (INIS)

    Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Mikic, N.; Tanaskovic, M.

    1996-01-01

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. Since the RA reactor is shutdown since 1984, it is high time for decision making of its future status. Possible solutions for the future status of the RA reactor discussed in this report are: renewal of reactor components for the reactor restart, conservation of the reactor (temporary shutdown) or permanent reactor shutdown. Control and maintenance of the reactor instrumentation and devices was done regularly but dependent on the availability of the spare parts and financial means. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor [sr

  20. Umatilla hatchery satellite facilities operation and maintenance. Annual report 1996

    International Nuclear Information System (INIS)

    Rowan, G.D.

    1997-06-01

    The Confederated Tribes of the Umatilla Indian Reservation (CTUIR) and Oregon Department of Fish and Wildlife (ODFW) are cooperating in a joint effort to enhance steelhead and re-establish salmon runs in the Umatilla River Basin. As an integral part of this program, Bonifer Pond, Minthorn Springs, Imeques C-mem-ini-kem and Thornhollow satellite facilities are operated for acclimation and release of juvenile summer steelhead (Oncorhynchus mykiss), fall and spring chinook salmon (O. tshawytscha) and coho salmon (O. kisutch). Minthorn is also used for holding and spawning adult summer steelhead and Three Mile Dam is used for holding and spawning adult fall chinook and coho salmon. Bonifer, Minthorn, Imeques and Thornhollow facilities are operated for acclimation and release of juvenile salmon and summer steelhead. The main goal of acclimation is to reduce stress from trucking prior to release and improve imprinting of juvenile salmonids in the Umatilla River Basin. Juveniles are transported to the acclimation facilities primarily from Umatilla and Bonneville Hatcheries. This report details activities associated with operation and maintenance of the Bonifer, Minthorn, Imeques, Thornhollow and Three Mile Dam facilities in 1996

  1. Systematization of Angra-1 operation attendance - Maintenance and periodic testings

    International Nuclear Information System (INIS)

    Furieri, E.B.; Carvalho Bruno, N. de; Salaverry, N.A.

    1988-01-01

    A maintenance analysis, their types and their functions for the safety of nuclear power plants is done. Programs and present trends in the reactor maintenance, as well as the maintenance program and periodic tests of Angra I, are analysed. The necessities of safety analysis and a systematization for maintenance attendance are discussed and the periodic testing as well as the attendance of international experience. (M.C.K.) [pt

  2. Operation and maintenance cost data for residential photovoltaic modules/panels

    Science.gov (United States)

    Oster, J. R., Jr.; Zaremski, D. R., Jr.; Albert, E. M.; Hawkins, S. L.

    1980-01-01

    Costs associated with the operation and maintenance of residential photovoltaic modules and arrays are studied. Six basic topics related to operation and maintenance to photovoltaic arrays are investigated: maintenance; cleaning; panel replacement; gasket repair/replacement; wiring repair/replacement; and termination repair/replacement. The effects of the mounting types (rack mount, stand off mount, direct mount and integral mount) and the installation/replacement type (sequential, partial interruption and independent) are identified and described. Methods of reducing maintenance costs are suggested.

  3. Water Distribution System Operation and Maintenance. A Field Study Training Program. Second Edition.

    Science.gov (United States)

    Kerri, Kenneth D.; And Others

    Proper installation, inspection, operation, maintenance, repair and management of water distribution systems have a significant impact on the operation and maintenance cost and effectiveness of the systems. The objective of this manual is to provide water distribution system operators with the knowledge and skills required to operate and maintain…

  4. An operational non destructive examination for ITER divertor plasma facing components

    Energy Technology Data Exchange (ETDEWEB)

    Durocher, A.; Escourbiac, F.; Farjon, J.L.; Vignal, N.; Cismondi, F. [Association Euratom-CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee; Merola, M. [ITER International Team, Cadarache, 13 - St Paul Lez Durance (France); Riccardi, B. [CEFDA CSU-Garching, Garching bei Munchen (Germany)

    2007-07-01

    Full text of publication follows: To meet the power exhaust - heat flux of 20 MW/m{sup 2} - requirements of Plasma Facing Components (PFCs) during plasma operation requires control of their thermal and mechanical integrity. As heat exhaust capability and lifetime of PFCs during in-situ operation are linked to the manufacturing quality, it is an absolute requirement to develop reliable nondestructive examination methods, in particular of the CFC-CuCrZr joint, throughout the manufacturing process. Within the framework of Tokamak Tore Supra upgrade, a pioneering activity has been developed to evaluate the capability of the PFC to be efficiently cooled. In 1998 a test bed - so called SATIR - based on the heat transient method was developed by the CEA and is used today as an inspection tool in order to guarantee the PFCs performances. The technical procurement plan of ITER Divertor targets stated that all Cu cast layers on CFC armour should be subjected to 100% thermographic examination. Each ITER Party should demonstrate its technical capability to carry out the PFC with the required cooling efficiently. The ITER Divertor PFCs pose new challenges especially for the mono-block CFC thickness, and the number of full scale units to be tested which is higher than on any existing or under construction fusion machine. The SATIR method as functional inspection has been identified as the basis test to decide upon the final acceptance of the Divertor PFCs. In order to increase the detection sensitivity of SATIR test bed, several possibilities have been assessed i) the increase of the convective heat transfer coefficient, which improved in a significant way the sensitivity of SATIR diagnostic on ITER components. ii) the installation of a digital infrared camera and the improvement of the thermal signal processing, has led to a considerable increase of performances iii) an innovative process based on spatial image autocorrelation will allow to localize the interlayer defect

  5. A software environment to execute automatic operational sequences on the ITER-FEAT DTP facility

    International Nuclear Information System (INIS)

    Fermani, G.; Zarfino, M.

    2001-01-01

    The divertor test platform (DTP) maintenance operations are carried out by means of the remote handling equipments (RHE), each dedicated to perform a set of specialised remote actions. Each RHE is controlled by an RHE control system (RHE-CS) and can be locally operated by an RHE-operator using the local control panel (LOP). To perform the maintenance activity, the DTP-operator coordinates the remote operations of every RHEs, using the supervisory system (DTP S S). Because the remote maintenance activities demand for a high degree of parallelism, automation and cooperation between various RHEs, the development of a software environment (OSAExE) that had the indicated characteristics has been necessary. The OSAExE environment is applicable to any distributed and cooperating system that is modelled as a set of autonomous subsystems. Each maintenance remote sequence needs to be modelled as a modified Petri-net diagram and subsequently 'compiled', in order to be automatically executed on OSAExE environment. The OSAExE architecture allows both, to program 'event driven' automatic sequences, and to maintain unchanged all the existing DTP S S features

  6. Temperature effect on hydrocarbon deposition on molybdenum mirrors under ITER-relevant long-term plasma operation

    NARCIS (Netherlands)

    Rapp, J.; van Rooij, G. J.; Litnovsky, A.; Marot, L.; De Temmerman, G.; Westerhout, J.; Zoethout, E.

    2009-01-01

    Optical diagnostics in ITER will rely on mirrors near the plasma and the deterioration of the reflectivity is a concern. The effect of temperature on the deposition efficiency of hydrocarbons under long-term operation conditions similar to ITER was investigated in the linear plasma generator

  7. Design of Mobile Operation and Maintenance System Based on Power GIS and GPS

    Directory of Open Access Journals (Sweden)

    Jing TAO

    2017-01-01

    Full Text Available In order to solve the low efficiency of operation and maintenance and the problems of management coordination caused by the coexistence of off-line operation and maintenance and multi system coexistence in current power telecommunication operation and maintenance, this paper proposes a mobile operation and maintenance system based on power GIS and GPS location technology. The system is based on the C/S architecture, and the mobile operation and maintenance terminal is connected with the operation and maintenance management terminal through wireless and wired network. In addition to meeting basic business requirements, the system integrates power GIS functions to visually demonstrate communication resources, personnel, and failures. The staff can use the wireless mobile terminal which integrated GPS module for to operate and maintain, and can locate accurately in real time.

  8. Operating and maintenance experience of Dhruva secondary shutdown system

    International Nuclear Information System (INIS)

    Sharma, U.L.; Bharathan, R.

    1997-01-01

    Nine numbers of cadmium shut-off rods are used as primary fast acting shutdown devices while moderator dumping is used as secondary shutdown system. The secondary shutdown system in Dhruva reactor comprises of 3 dump valves and 3 control valves. Under normal operations, the control valves are used to control the moderator level and thereby the reactor power. Under Trip conditions the dump valves as well as the control valves open fully, dumping the moderator to the dump tank, thereby acting as secondary shutdown devices. While the failure of any of these valves to close fully is an incident, the failure of any of these valves to open on a demand is a safety related unusual occurrence and needs to be viewed seriously. During the last 11 years of operation of these valves, there was one incidence of a valve not closing fully and there were two instances of a valve not opening fully on demand. The possible causes, the corrective action taken to rehabilitate these valves and the elaborate system preparations undertaken to enable maintenance jobs are described. (author)

  9. Integrated approach to optimize operation and maintenance costs for operating nuclear power plants

    International Nuclear Information System (INIS)

    2006-06-01

    In the context of increasingly open electricity markets and the 'unbundling' of generating companies from former utility monopolies, an area of major concern is the economic performance of the existing fleet of nuclear power plants. Nuclear power, inevitably, must compete directly with other electricity generation sources. Coping with this competitive pressure is a challenge that the nuclear industry should meet if the nuclear option is to remain a viable one. This competitive environment has significant implications for nuclear plant operations, including, among others, the need for the more cost effective management of plant activities, and the greater use of analytical tools to balance the costs and benefits of proposed activities, in order to optimize operation and maintenance costs, and thus insure the economic competitiveness of existing nuclear power plants. In the framework of the activities on Nuclear Economic Performance Information System (NEPIS), the IAEA embarked in developing guidance on optimization of operation and maintenance costs for nuclear power plants. The report was prepared building on the fundamental that optimization of operation and maintenance costs of a nuclear power plant is a key component of a broader integrated business strategic planning process, having as overall result achievement of organization's business objectives. It provides advice on optimization of O and M costs in the framework of strategic business planning, with additional details on operational planning and controlling. This TECDOC was elaborated in 2004-2005 in the framework of the IAEA's programme on Nuclear Power Plant Operating Performance and Life Cycle Management, with the support of two consultants meetings and one technical meeting and based on contributions provided by participants. It can serve as a useful reference for the management and operation staff within utilities, nuclear power plant operators and regulators and other organizations involved in

  10. The International Thermonuclear Experimental Reactor (ITER) international organisation: which laws apply to this international nuclear operator?

    International Nuclear Information System (INIS)

    Grammatico-Vidal, L.

    2009-01-01

    ITER is being carried out by way of international collaboration between seven partners (the European atomic energy community -EURATOM-, China, India, Japan, Russia, south korea and the United states) which together represent more than half the world population. From a project organisation point of view, it is supported by both financial and in-kind contributions provided by each of the partner; each member makes its contribution through a special legal entity called a 'domestic agency' to an international organisation which was set up by the Agreement on the Establishment of an International Fusion Energy Organization for the joint Implementation of the ITER project signed in Paris on 21. november 2006 and which entered into force on 24. october 2007 after ratification by each of the partners. The international agreement is to remain in effect for a period of 35 years and may be renewed for a period of 10 years without any change to its content. It is supplemented by an agreement of the same date on the privileges and immunities of the organisation and of its staff. The function of the ITER organisation is to construct, commission, operate and permanently shutdown the ITER facility, to encourage their exploitation by laboratories, other institutions and personnel participating in the fusion energy research and development programmes of its members and to promote public understanding and acceptance of fusion energy. The unique institutional structure for this project will be described briefly in the introduction before analysing the law applicable to this international organisation, a French nuclear operator, unique in France today. (N.C.)

  11. Cask operation and maintenance for spent fuel storage

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.S. [International Atomic Energy Agency, Vienna (Austria)

    2004-07-01

    Interim storage is an essential platform for any option to be chosen later as an endpoint for spent fuel management. In view of such a circumstance, the most imminent service required for the spent fuel management worldwide is to provide adequate storage for the future spent fuel inventory arising either from the continued operation of nuclear power plants or from the removal of spent fuel in preparation for plant decommissioning. While the bulk of the global inventory of spent fuel are still stored in AR pools, dry storage has become a prominent alternative especially for newly built AFR facilities, with more than 17,000 t HM already stored in dry storage facilities worldwide. Storage in cask under inert conditions has become the preferred option, given the advantages including passive cooling features and modular mode of capacity increase. In terms of economics, dry storage is particularly propitious for long-term storage in that operational costs are minimized by the passive cooling features. The trend toward dry storage, especially in cask type, is likely to continue with an implication that and the supply will closely follow the increasing demand for storage by incremental additions of casks to the effect of minimizing cost penalty of the idle capacities typical of pool facilities. A variety of storage systems have been developed to meet specific requirements of different reactor fuels and a large number of designs based on these generic technologies are now available for the spent fuel containers (horizontal, vertical etc) and storage facilities. Multi-purpose technologies (i.e. a single technology for storage, transportation and disposal) have also been studied. Recent concern on security measures for protection of spent fuel has prompted a consideration on the possibility of placing storage facility underground. The future evolution of requirements and technologies will bring important impacts on cask operation and maintenance for spent fuel storage.

  12. Cask operation and maintenance for spent fuel storage

    International Nuclear Information System (INIS)

    Lee, J.S.

    2004-01-01

    Interim storage is an essential platform for any option to be chosen later as an endpoint for spent fuel management. In view of such a circumstance, the most imminent service required for the spent fuel management worldwide is to provide adequate storage for the future spent fuel inventory arising either from the continued operation of nuclear power plants or from the removal of spent fuel in preparation for plant decommissioning. While the bulk of the global inventory of spent fuel are still stored in AR pools, dry storage has become a prominent alternative especially for newly built AFR facilities, with more than 17,000 t HM already stored in dry storage facilities worldwide. Storage in cask under inert conditions has become the preferred option, given the advantages including passive cooling features and modular mode of capacity increase. In terms of economics, dry storage is particularly propitious for long-term storage in that operational costs are minimized by the passive cooling features. The trend toward dry storage, especially in cask type, is likely to continue with an implication that and the supply will closely follow the increasing demand for storage by incremental additions of casks to the effect of minimizing cost penalty of the idle capacities typical of pool facilities. A variety of storage systems have been developed to meet specific requirements of different reactor fuels and a large number of designs based on these generic technologies are now available for the spent fuel containers (horizontal, vertical etc) and storage facilities. Multi-purpose technologies (i.e. a single technology for storage, transportation and disposal) have also been studied. Recent concern on security measures for protection of spent fuel has prompted a consideration on the possibility of placing storage facility underground. The future evolution of requirements and technologies will bring important impacts on cask operation and maintenance for spent fuel storage

  13. Economic implications of nuclear operating and maintenance costs

    International Nuclear Information System (INIS)

    Braun, C.

    1994-01-01

    Nuclear operating and maintenance (O and M) costs for U.S. plants have been increasing during the decade of the 1980's. Costs have stabilized over the last five years but have not yet significantly declined. Annual capacity factors have considerably improved during the last eight years and unit O and M costs expressed in Mills Kwh have thus declined. Two other important trends evident over the last five years have been the decline in fossil fuel prices and the transition to deregulated electric utilities market, accelerated with the passage of the 1992 Energy Policy Act. Within the next five years it may be possible for large scale industrial customers to directly contract with electricity generators, by they utilities or independent power producers (IPP's) for supplying their power requirements. The ability of such customers to directly contract with potential supplies based on low cost performance bypassing their local utility, may have significant implications for the structure of the utility industry in the near term and for plant operations. A greater pressure will likely be exerted on all plants, including nuclear to reduce operating costs so as to remain competitive with other power suppliers in their markets. Nuclear O and M costs are likely to be heavily scrutinized for possible savings and reductions. The electric utilities mergers waves and the nuclear industry's initiative on O and M cost control both aim at improving plant economics so as to better compete in the more deregulated environment. In this climate the issues of why nuclear O and M costs have increased, what can be done to reduce costs and what are the implications for advanced reactors design and economics are discussed. 14 figs

  14. Risk-Based Operation and Maintenance of Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Nielsen, Jannie Sønderkær

    For offshore wind turbines, maintenance costs are substantial due to a large number of component failures. In addition to the repair costs, equipment costs and lost production costs are large due to limited accessibility to the turbines. In order to reduce the costs, preventive methods can be used......, but presently maintenance is not planned using advanced methods taking all available information into account in a consistent manner. Maintenance decisions can be made based on risk-based methods, where the total expected life cycle costs are minimized. Methods have been developed for assessing the corrective...... maintenance costs, and many studies have also been published for preventive maintenance. However, an important part is the modeling of the relationship between maintenance and reliability, which is typically not modeled in a consistent way. Therefore, the methods cannot be used directly for optimal...

  15. survey of operators kn and maintenance o in ebonyi st vey

    African Journals Online (AJOL)

    eobe

    o access the operators' knowledge of operation and maintenance of farm to access the operators' .... other factors hinder agricultural mechanization in Nigeria. Ebonyi State is an agrarian area, hence, the ... MATERIALS AND METHODS. 2.

  16. Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Norm Stanley

    2011-02-01

    This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

  17. 43 CFR 404.55 - Who is responsible for the operation, maintenance, and replacement costs?

    Science.gov (United States)

    2010-10-01

    ... Miscellaneous § 404.55 Who is responsible for the operation, maintenance, and replacement costs? You will be responsible for 100 percent of the operation, maintenance, and replacement costs for any rural water facility... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Who is responsible for the operation...

  18. Augmented reality aided operation and maintenance system for indoor environments

    International Nuclear Information System (INIS)

    Tamura, Yuichi; Umetani, Tomohiro; Kubo, Shin

    2013-01-01

    This paper proposes an Augmented Reality (AR) system to assist operation and maintenance tasks in an indoor environment, such as a nuclear fusion reactor and its building. AR is a technology that enhances real information by adding 3D virtual objects, images, sounds, or movies via a web camera. The AR system often uses “markers” such as QR code to detect the place where the virtual content should appear. However, these markers are unnatural and they can disturb the scenery. We propose an AR system that can detect natural markers, which provides AR content via a network. This system stores the information related to markers and virtual objects on a server. A device connected to this system automatically downloads this content so that the user can watch the AR content via a web camera. We add a real-time numerical simulation function that allows us to simulate physical phenomena by touching AR contents. It also enables us to observe simulation results by downloading a movie of numerical simulation results from the simulation server. Overall, this system allows us to watch the same content with multiple devices and to simulate physical phenomena using various parameters. (author)

  19. Preventive Maintenance. FMO: Fundamentals of Machine Operation. Third Edition.

    Science.gov (United States)

    Hathaway, Louis

    This text is intended to provide students with basic information on conducting preventive maintenance on agricultural machinery. The following topics are covered in the individual chapters: the importance of preventive maintenance and recommended service intervals; engine intake and exhaust systems (air cleaners, turbochargers, intake and exhaust…

  20. Feasibility study of the cut and weld operations by RH on the cooling pipes of ITER NB components

    International Nuclear Information System (INIS)

    Pineiro, Oscar; Fernandez, Carlos; Medrano, Mercedes; Liniers, Macarena; Botija, Jose; Alonso, Javier; Sarasola, Xabier; Damiani, Carlo

    2009-01-01

    The maintenance operations of ITER NB components inside the vessel - Beam Line Components (BLC's) involve the removal of the faulty component, its transport to the hot cell as well as the reverse operations of transport of the repaired/new component and its reinstallation inside the vessel. Prior to the removal of the BLC's the cooling pipes must be detached from the component following a procedure that applies to the cutting of the pipes and subsequent welding when the component is re-installed. The purpose of this study, conducted in the framework of EFDA, is to demonstrate the feasibility of the cut and weld operations on the water pipes of the BLC's using fully remote handling techniques. Viable technologies for the cut and weld operations have been identified within the study; in particular the following aspects will be presented in the paper: - Different strategies can be pursued in the detachment of the components depending on the number of cut and weld operations to be performed on the pipes. The selected strategy will impact on the procedure to be followed likewise on important aspects as the requirements of the flexible joints assembled on the pipes. - The existing cutting techniques have been examined in the light of the remotely performed pipe cutting at the NB cell. Modifications of commercial tools have been proposed in order to adapt them to the BLC's pipes requirements. The debris produced during the cutting process must be controlled and collected, therefore a cleaning system has been integrated in the adapted cutting tool referred above. - The existing welding techniques have been also examined and compared based on different criteria such as complexity, reliability, alignment tolerances, etc. TIG welding is the preferred technique as it stands out for its superior performance. The commercial tools identified need to be adapted to the NB environment. - The alignment of the pipes is a critical issue concerning the remote welding. A proper alignment

  1. Operation and maintenance support expert systems for BWR nuclear power plants

    International Nuclear Information System (INIS)

    Miyazawa, Tatsuo; Hayakawa, Hiroyasu; Fukutomi, Shigeki

    1990-01-01

    Toshiba has been developing expert systems for operation and maintenance support in BWRs. These expert systems are designed to be integrated with conventional plant monitoring systems, and maintenance management systems to provide both comprehensive and powerful support capabilities. Some of these expert systems are already being used on a trial basis both within Toshiba and in electric power utility companies. This paper describes expert systems for the support of plant and equipment monitoring, maintenance scheduling, and maintenance work procedure planning. (author)

  2. Seventh meeting of the ITER physics expert group on energetic particles, heating and steady state operations

    International Nuclear Information System (INIS)

    Gormezano, C.

    1999-01-01

    The seventh meeting of the ITER Physics Group on energetic particles, heating and steady state operation was held at CEN/Cadarache from 14 to 18 September 1999. This was the first meeting following the redefinition of the Expert Group structure and it was also the first meeting without participation of US physicists. The main topics covered were: 1. Energetic Particles, 2. Ion Cyclotron Resonance Heating, 3. Lower Hybrid Current Drive, 4. Electron Cyclotron Resonance Heating and Current Drive, 5. Neutral Beam Injection, 6. Steady-State Aspects

  3. RTO/RC ITER plasma performance: inductive and steady-state operation

    International Nuclear Information System (INIS)

    Mukhovatov, V.; Boucher, D.; Fujisawa, N.; Shimada, M.; Vayakis, G.; Janeschitz, G.; Matsumoto, H.; Leonov, V.; Polevoy, A.

    2000-01-01

    The plasma performance in two design options of the reduced-technical objectives/reduced cost (RTO/RC) ITER, i.e. IAM (intermediate aspect ratio machine) and LAM (low aspect ratio machine) is analysed. It is shown that Q=P fus /P aux ∼10 can be obtained in both options at inductively driven ELMy H-mode operation. The operation domain in LAM is found to be marginally larger than that in IAM. The non-inductive operation with Q approx.= 5 will be possible in both machines, provided a large amount of power with a high current drive efficiency is applied, or substantial improvement of the energy confinement time relative to the ELMy H-mode (H H =1.2-1.4) is obtained. The required values of H H and β N are marginally smaller in IAM. The IAM-like machine, ITER-FEAT (fusion energy advanced tokamak), proposed for a detailed engineering design is discussed in brief. (author)

  4. The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER

    Energy Technology Data Exchange (ETDEWEB)

    Grosman, André, E-mail: andre.grosman@cea.fr [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Bucalossi, Jérôme; Doceul, Louis [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Escourbiac, Frédéric [ITER Organization, Cadarache, 13115 St. Paul-lez-Durance (France); Lipa, Manfred [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Merola, Mario [ITER Organization, Cadarache, 13115 St. Paul-lez-Durance (France); Missirlian, Marc [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Pitts, Richard A. [ITER Organization, Cadarache, 13115 St. Paul-lez-Durance (France); Samaille, Franck; Tsitrone, Emmanuelle [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France)

    2013-10-15

    Highlights: ► The WEST programme is a unique opportunity to experience the industrial scale manufacture of tungsten plasma-facing components similar to the ITER divertor ones. ► In Tore Supra, it will bring important know how for actively cooled W divertor operation. ► This can be done by a reasonable modification of the Tore Supra tokamak. ► A fast implementation of the project would make this information available in due time. ► This allows a significant contribution to the W ITER divertor risk minimization in its manufacturing and operation phase. -- Abstract: The WEST programme consists in transforming the Tore Supra tokamak into an X point divertor device, while taking advantage of its long discharge capability. This is obtained by inserting in vessel coils to create the X point while adapting the in-vessel elements to this new geometry. This will allow the full tungsten divertor technology to be used on ITER to be tested in anticipation of its use on ITER under relevant heat loading conditions and pulse duration. The early manufacturing of a significant industrial series of ITER-similar W plasma-facing units will contribute to the ITER divertor manufacturing risk mitigation and to that associated with early W divertor plasma operation on ITER.

  5. Operations Research Models for Scheduling Railway Infrastructure Maintenance

    NARCIS (Netherlands)

    G. Budai-Balke (Gabriella)

    2009-01-01

    textabstractIn the last decades, maintenance of technical systems has become increasingly impor- tant in many industries. Such systems are transport systems (rail, bus, airplane), civil engineering systems (roads, buildings, bridges), health care (hospitals), communication systems, manufacturing

  6. Iterative deblending of simultaneous-source data using a coherency-pass shaping operator

    Science.gov (United States)

    Zu, Shaohuan; Zhou, Hui; Mao, Weijian; Zhang, Dong; Li, Chao; Pan, Xiao; Chen, Yangkang

    2017-10-01

    Simultaneous-source acquisition helps greatly boost an economic saving, while it brings an unprecedented challenge of removing the crosstalk interference in the recorded seismic data. In this paper, we propose a novel iterative method to separate the simultaneous source data based on a coherency-pass shaping operator. The coherency-pass filter is used to constrain the model, that is, the unblended data to be estimated, in the shaping regularization framework. In the simultaneous source survey, the incoherent interference from adjacent shots greatly increases the rank of the frequency domain Hankel matrix that is formed from the blended record. Thus, the method based on rank reduction is capable of separating the blended record to some extent. However, the shortcoming is that it may cause residual noise when there is strong blending interference. We propose to cascade the rank reduction and thresholding operators to deal with this issue. In the initial iterations, we adopt a small rank to severely separate the blended interference and a large thresholding value as strong constraints to remove the residual noise in the time domain. In the later iterations, since more and more events have been recovered, we weaken the constraint by increasing the rank and shrinking the threshold to recover weak events and to guarantee the convergence. In this way, the combined rank reduction and thresholding strategy acts as a coherency-pass filter, which only passes the coherent high-amplitude component after rank reduction instead of passing both signal and noise in traditional rank reduction based approaches. Two synthetic examples are tested to demonstrate the performance of the proposed method. In addition, the application on two field data sets (common receiver gathers and stacked profiles) further validate the effectiveness of the proposed method.

  7. Software protocol design: Communication and control in a multi-task robot machine for ITER vacuum vessel assembly and maintenance

    International Nuclear Information System (INIS)

    Li, Ming; Wu, Huapeng; Handroos, Heikki; Yang, Guangyou; Wang, Yongbo

    2015-01-01

    applying these protocols, the software for a multi-task robot machine that is used for ITER vacuum vessel assembly and maintenance has been developed and it is demonstrated that machining tasks of the robot machine, such as milling, drilling, welding etc., can be implemented in both an individual and composite way.

  8. Software protocol design: Communication and control in a multi-task robot machine for ITER vacuum vessel assembly and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Li, Ming, E-mail: ming.li@lut.fi [Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland); Wu, Huapeng; Handroos, Heikki [Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland); Yang, Guangyou [School of Mechanical Engineering, Hubei University of Technology, Wuhan (China); Wang, Yongbo [Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland)

    2015-10-15

    applying these protocols, the software for a multi-task robot machine that is used for ITER vacuum vessel assembly and maintenance has been developed and it is demonstrated that machining tasks of the robot machine, such as milling, drilling, welding etc., can be implemented in both an individual and composite way.

  9. Maintenance-based prognostics of nuclear plant equipment for long-term operation

    Energy Technology Data Exchange (ETDEWEB)

    Welz, Zachary; Coble, Jamie; Upadhyaya, Belle; Hines, Wes [University of Tennessee, Knoxville (United States)

    2017-08-15

    While industry understands the importance of keeping equipment operational and well maintained, the importance of tracking maintenance information in reliability models is often overlooked. Prognostic models can be used to predict the failure times of critical equipment, but more often than not, these models assume that all maintenance actions are the same or do not consider maintenance at all. This study investigates the influence of integrating maintenance information on prognostic model prediction accuracy. By incorporating maintenance information to develop maintenance-dependent prognostic models, prediction accuracy was improved by more than 40% compared with traditional maintenance-independent models. This study acts as a proof of concept, showing the importance of utilizing maintenance information in modern prognostics for industrial equipment.

  10. Optimal, Risk-based Operation and Maintenance Planning for Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard

    2008-01-01

    For offshore wind turbines costs to operation and maintenance are substantial. This paper describes a risk-based life-cycle approach for optimal planning of operation and maintenance. The approach is based on pre-posterior Bayesian decision theory. Deterioration mechanisms such as fatigue...

  11. 43 CFR 426.23 - Recovery of operation and maintenance (O&M) costs.

    Science.gov (United States)

    2010-10-01

    ... operation and maintenance (O&M) costs. (a) General. All new, amended, and renewed contracts shall provide... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Recovery of operation and maintenance (O&M) costs. 426.23 Section 426.23 Public Lands: Interior Regulations Relating to Public Lands BUREAU OF...

  12. Best Practices in Photovoltaic System Operations and Maintenance: 2nd Edition

    Energy Technology Data Exchange (ETDEWEB)

    Whaley, Cass [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2016-12-01

    This best practices guide encourages high-quality system deployment and operation that improves lifetime project performance and energy production while reducing, or at least optimizing, costs to deliver an operation and maintenance program.

  13. The method for assurance to operational safety of cryogenics equipment through definite maintenance

    International Nuclear Information System (INIS)

    Anghel, Vasile

    2004-01-01

    The present paper reports about a method of ensuring operational safety of cryogenics equipment through specific maintenance measures which imply a definite concept of maintainability and operational reliability, methods of maintenance, necessary logistic and necessary personnel. The stages of the concept should succeed in a logical order and must be based on detailed analyses of the process of maintenance. The method starts from the operation conditions of cryogenic equipment in nuclear regime. Thus maintenance policy must be well defined within the boundaries of the nuclear plant through definition of coherent objectives and responsibility delegation for the personnel implied in maintenance activity. This method ensures performance in maintenance and an efficient feedback from equipment analysis. (author)

  14. ITER SAFETY TASK NID-5D: Operational tritium loss and accident investigation for heat transport and water detritiation systems

    International Nuclear Information System (INIS)

    Kalyanam, K.M.; Fong, C.; Moledina, M.; Natalizio, A.

    1995-02-01

    The task objectives are to: a) determine major pathways for tritium loss during normal operation of the cooling systems and water detritiation system, b) estimate operational losses and environmental tritium releases from the heat transport and water detritiation systems of ITER, and c) prepare a preliminary Failure Modes and Effects Analysis (FMEA) for the ITER Water Detritiation System. The analysis will be used to estimate chronic environmental tritium releases (airborne and waterborne) for the ITER Cooling Systems and Water Detritiation System. The assessment will form the basis for demonstrating the acceptability of ITER for siting in the Early Safety and Environmental Characterization Study (ESECS), to be issued in early 1995. (author). 7 refs., 10 tabs., 11 figs

  15. Operations & Maintenance Best Practices - A Guide to Achieving Operational Efficiency (Release 3)

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, Greg; Pugh, Ray; Melendez, Aldo P.; Hunt, W. D.

    2010-08-04

    This guide highlights operations and maintenance programs targeting energy and water efficiency that are estimated to save 5% to 20% on energy bills without a significant capital investment. The purpose of this guide is to provide you, the Operations and Maintenance (O&M)/Energy manager and practitioner, with useful information about O&M management, technologies, energy and water efficiency, and cost-reduction approaches. To make this guide useful and to reflect your needs and concerns, the authors met with O&M and Energy managers via Federal Energy Management Program (FEMP) workshops. In addition, the authors conducted extensive literature searches and contacted numerous vendors and industry experts. The information and case studies that appear in this guide resulted from these activities. It needs to be stated at the outset that this guide is designed to provide information on effective O&M as it applies to systems and equipment typically found at Federal facilities. This guide is not designed to provide the reader with step-by-step procedures for performing O&M on any specific piece of equipment. Rather, this guide first directs the user to the manufacturer's specifications and recommendations. In no way should the recommendations in this guide be used in place of manufacturer's recommendations. The recommendations in this guide are designed to supplement those of the manufacturer, or, as is all too often the case, provide guidance for systems and equipment for which all technical documentation has been lost. As a rule, this guide will first defer to the manufacturer's recommendations on equipment operation and maintenance.

  16. Risk-Based Operation and Maintenance of Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Nielsen, Jannie Sønderkær

    to oil and gas structures. In addition, condition monitoring systems are often available, and the information should be taken into account when making decisions. In this thesis, methods for risk-based maintenance planning using Bayesian methods are investigated, with the aim of making optimal decisions......, but presently maintenance is not planned using advanced methods taking all available information into account in a consistent manner. Maintenance decisions can be made based on risk-based methods, where the total expected life cycle costs are minimized. Methods have been developed for assessing the corrective...... considering all available information. First, a theoretical damage model is formulated, the model is then updated using condition monitoring data, and the updated model is used as basis for risk-based decision making. Several approaches for solving the decision problems have been considered: various types...

  17. Low cycle fatigue behavior of ITER-like divertor target under DEMO-relevant operation conditions

    Energy Technology Data Exchange (ETDEWEB)

    Li, Muyuan; Werner, Ewald [Lehrstuhl für Werkstoffkunde und Werkstoffmechanik, Technische Universität München, Boltzmannstr. 15, 85748 Garching (Germany); You, Jeong-Ha, E-mail: you@ipp.mpg.de [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany)

    2015-01-15

    Highlights: • LCF behavior of the cooling tube and the interlayer of an ITER-like divertor target is studied. • For the cooling tube, LCF failure will not be an issue under an HHF load of up to 18 MW/m{sup 2}. • Plastic strain in the interlayer is concentrated at the free surface edge of the bond interface. • The predicted LCF lifetime of the interlayer may not meet the design requirement. - Abstract: In this work the low cycle fatigue (LCF) behavior of the copper alloy cooling tube and the copper interlayer of an ITER-like divertor target is reported for nine different combinations of loading and cooling conditions relevant to DEMO divertor operation. The LCF lifetime is presented as a function of loading and cooling conditions considered here by means of cyclic plasticity simulation and using LCF data of materials relevant for ITER. The numerical predictions indicate, that fatigue failure will not be an issue for the copper alloy tube under a high heat flux (HHF) load of up to 18 MW/m{sup 2} as long as it preserves its initial strength. In contrast, the copper interlayer exhibits significant plastic dissipation at the free surface edge of the bond interface adjacent to the cooling tube, where the LCF lifetime is predicted to be below 3000 load cycles for HHF loads higher than 15 MW/m{sup 2}. Most of the bulk region of the copper interlayer away from the free surface edge does not experience severe plastic fatigue and hence does not pose any critical concern as the LCF lifetime is predicted to be at least 7000 load cycles. LCF lifetime decreases as HHF load is increased or coolant temperature is decreased.

  18. Risk-Based Operation and Maintenance Using Bayesian Networks

    DEFF Research Database (Denmark)

    Nielsen, Jannie Jessen; Sørensen, John Dalsgaard

    2011-01-01

    This paper describes how risk-based decision making can be used for maintenance planning of components exposed to degradation such as fatigue in offshore wind turbines. In fatigue models, large epistemic uncertainties are usually present. These can be reduced if monitoring results are used to upd...

  19. Possibility of Q>5 stable, steady-state operation in ITER with moderate βN and H-factor

    International Nuclear Information System (INIS)

    Polevoi, A.R.; Mukhovatov, V.S.; Shimada, M.; Medvedev, S.Yu.; Ivanov, A.A.; Poshekhonov, Yu.Yu.; Pustovitov, V.D.; Chu, M.S.

    2003-01-01

    A possibility of steady state stable operation in ITER with Q>5 and moderate requirements for plasma confinement is investigated. It is shown that there is some parametrical space for such operation where the ideal kink modes could be stabilised by the first wall. It is found that operational space where the ideal kink modes can be stabilised by the conducting wall could be noticeably extended by a relatively small reduction of the pressure peaking factor. The resistive wall mode stabilisation in ITER is discussed. (author)

  20. ITER task title - source term data, modelling, and analysis. ITER subtask no. S81TT05/5 (SEP 1-1). Global tritium source term analysis basis document. Subtask 1: operational tritium effluents and releases. Final report (1995 TASK)

    International Nuclear Information System (INIS)

    Kalyanam, K.M.

    1996-06-01

    This document represents the final report for the global tritium source term analysis task initiated in 1995. The report presents a room-by-room map/table at the subsystem level for the ITER tritium systems, identifying the major equipment, secondary containments, tritium release sources, duration/frequency of tritium releases and the release pathways. The chronic tritium releases during normal operation, as well as tritium releases due to routine maintenance of the Water Distillation Unit, Isotope Separation System and Primary and Secondary Heat Transport Systems, have been estimated for most of the subsystems, based on the IDR design, the Design Description Documents (April - Jun 1995 issues) and the design updates up to December 1995. The report also outlines the methodology and the key assumptions that are adopted in preparing the tritium release estimates. The design parameters for the ITER Basic Performance Phase (BPP) have been used in estimating the tritium releases shown in the room-by-room map/table. The tritium release calculations and the room-by-room map/table have been prepared in EXCEL, so that the estimates can be refined easily as the design evolves and more detailed information becomes available. (author). 23 refs., tabs

  1. Control-limit preventive maintenance policies for components subject to imperfect preventive maintenance and variable operational conditions

    International Nuclear Information System (INIS)

    You Mingyi; Li Hongguang; Meng Guang

    2011-01-01

    This paper develops two component-level control-limit preventive maintenance (PM) policies for systems subject to the joint effect of partial recovery PM acts (imperfect PM acts) and variable operational conditions, and investigates the properties of the proposed policies. The extended proportional hazards model (EPHM) is used to model the system failure likelihood influenced by both factors. Several numerical experiments are conducted for policy property analysis, using real lifetime and operational condition data and typical characterization of imperfect PM acts and maintenance durations. The experimental results demonstrate the necessity of considering both factors when they do exist, characterize the joint effect of the two factors on the performance of an optimized PM policy, and explore the influence of the loading sequence of time-varying operational conditions on the performance of an optimized PM policy. The proposed policies extend the applicability of PM optimization techniques.

  2. Condition-based dynamic maintenance operations planning and grouping. Application to commercial heavy vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Bouvard, K., E-mail: keomany.bouvard@volvo.co [Volvo Technology, 99 route de Lyon, 69806 Saint Priest cedex (France); Laboratoire d' Automatique de Genie Informatique et Signal - FRE3303 - Polytech' Lille, 59655 Villeneuve d' Ascq (France); Artus, S., E-mail: samuel.artus@volvo.co [Volvo Technology, 99 route de Lyon, 69806 Saint Priest cedex (France); Berenguer, C., E-mail: christophe.berenguer@utt.f [Universite de technologie de Troyes - Institut Charles Delaunay and UMR CNRS 6279 - 12, rue Marie Curie, BP2060, 10010 Troyes cedex (France); Cocquempot, V., E-mail: vincent.cocquempot@univ-lille1.f [Laboratoire d' Automatique de Genie Informatique et Signal - FRE3303 - Polytech' Lille, 59655 Villeneuve d' Ascq (France)

    2011-06-15

    This paper aims at presenting a method to optimize the maintenance planning for a commercial heavy vehicle. Such a vehicle may be considered as a multi-components system. Grouping maintenance operations related to each component reduces the global maintenance cost of the system. Classically, the optimization problem is solved using a priori reliability characteristics of components. Two types of methods may be used, i.e. static or dynamic methods. Static methods provide a fixed maintenance planning, whereas dynamic methods redefine the groups of maintenance operations at each decision time. Dynamic procedures can incorporate component information such as component states or detected failures. For deteriorating systems, reliability characteristics of each component may be estimated thanks to deterioration models and may be updated when a degradation measure is available. This additional information on degradation features allows to better follow the real state of each component and to improve the maintenance planning.

  3. Performance test of diamond-like carbon films for lubricating ITER blanket maintenance equipment under GPa-level high contact stress

    International Nuclear Information System (INIS)

    Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Shibanuma, Kiyoshi

    2007-01-01

    Diamond-like carbon (DLC) coating was tested as a candidate solid lubricant for transmission gears of the maintenance equipment of the blanket of the ITER instead of an oil lubricant. The wear tests using the pin-on-disk method were performed on disks with SCM440 and SNCM420 as the base materials and coated with soft, layered, and hard DLCs. All cases satisfied the required allowable contact stress (2 GPa) and lifetime (10 4 cycles), and therefore the feasibility of the DLC coating was validated. Among the three types of DLCs, the soft DLC showed the best performance. (author)

  4. Evaluating ITER remote handling middleware concepts

    NARCIS (Netherlands)

    Koning, J. F.; Heemskerk, C. J. M.; Schoen, P.; Smedinga, D.; Boode, A. H.; Hamilton, D. T.

    2013-01-01

    Remote maintenance activities in ITER will be performed by a unique set of hardware systems, supported by an extensive software kit. A layer of middleware will manage and control a complex set of interconnections between teams of operators, hardware devices in various operating theatres, and

  5. The impact of digitalization on Property Operations and Maintenance (O&M)

    OpenAIRE

    Garcia, Resty Gonzales

    2017-01-01

    The research topic of this master thesis is; “How can digitalization help increase productivity in property Operations and Maintenance (O&M)?” The research topic focuses on the challenges and opportunities in utilizing Computer Aided Facilities Management (CAFM) system regarding the operative function in Operations and Maintenance (O&M). The purpose of this research work is to analyze relevant literature and empirical data on how digitalization affects the O&M process and how the O&M ...

  6. UNC Nuclear Industries' human-factored approach to the operating or maintenance procedure

    International Nuclear Information System (INIS)

    Nelson, A.A.; Clark, J.E.

    1982-01-01

    The development of Human Factors Engineering (HFE) and UNC Nuclear Industries' (UNC) commitment to minimizing the potential for human error in the performance of operating or maintenance procedures have lead to a procedure upgrade program. Human-factored procedures were developed using information from many sources including, but not limited to, operators, a human factors specialist, engineers and supervisors. This has resulted in the Job Performance Aid (JPA). This paper presents UNC's approach to providing human-factored operating and maintenance procedures

  7. Lower hybrid heating and current drive in Iter operation scenarios and outline system design

    International Nuclear Information System (INIS)

    1994-11-01

    Lower Hybrid Waves (LHW) are considered a valid method of plasma heating and the best demonstrated current drive method. Current drive by LHW possesses the unique feature, as compared to the other methods, to retain a good current drive efficiency in plasma regions of low to medium temperature, or in low-β phases of the discharges. This makes them an essential element to realize the so called 'advanced steady-state Tokamak scenarios' in which a hollow current density profile (deep shear reversal) - established during the ramp-up of the plasma current - offers the prospects of improved confinement and an MHD-stable route to continuous burn. This report contains both modelling and design studies of an LHW system for ITER. It aims primarily at the definition of concepts and parameters for steady-state operation using LHW combined with Fast Waves (FW), or other methods of generating a central seed current for high bootstrap current operation. However simulations addressing the use of LHW for current profile control in the high current pulsed operation scenario are also presented. The outline design of a LHW system which covers the needs for both pulsed and steady-state operation is described in detail. (author). 28 refs., 49 figs

  8. Information operator approach and iterative regularization methods for atmospheric remote sensing

    International Nuclear Information System (INIS)

    Doicu, A.; Hilgers, S.; Bargen, A. von; Rozanov, A.; Eichmann, K.-U.; Savigny, C. von; Burrows, J.P.

    2007-01-01

    In this study, we present the main features of the information operator approach for solving linear inverse problems arising in atmospheric remote sensing. This method is superior to the stochastic version of the Tikhonov regularization (or the optimal estimation method) due to its capability to filter out the noise-dominated components of the solution generated by an inappropriate choice of the regularization parameter. We extend this approach to iterative methods for nonlinear ill-posed problems and derive the truncated versions of the Gauss-Newton and Levenberg-Marquardt methods. Although the paper mostly focuses on discussing the mathematical details of the inverse method, retrieval results have been provided, which exemplify the performances of the methods. These results correspond to the NO 2 retrieval from SCIAMACHY limb scatter measurements and have been obtained by using the retrieval processors developed at the German Aerospace Center Oberpfaffenhofen and Institute of Environmental Physics of the University of Bremen

  9. Comparison of all-remote and personnel access maintenance operations for INTOR

    International Nuclear Information System (INIS)

    Spampinato, P.T.; Finn, P.A.; Gohar, M.Y.; Stasko, R.R.

    1985-01-01

    The INTOR reference design was developed to permit limited maintenance operations external to the reactor in a ''hands-on'' mode; all internal operations would be remotely accomplished. The design embodies those requirements for shielding, tritium containment and cleanup, and confinement of contaminated particulate matter to permit personnel access. The cost reflects these requirements, at least first order. The impact of personnel access on the reactor design and its costs are cause to reexamine the maintenance approach on which much of the present configuration is based. The purpose of this study is to compare the benefits and costs associated with personnel access maintenance procedures to those associated with all-remote maintenance procedures and to identify modifications to the baseline design that could enhance maintenance operations

  10. Value centric approaches to the design, operations and maintenance of wind turbines

    Science.gov (United States)

    Khadabadi, Madhur Aravind

    Wind turbine maintenance is emerging as an unexpectedly high component of turbine operating cost, and there is an increasing interest in managing this cost. This thesis presents an alternative view of maintenance as a value-driver, and develops an optimization algorithm to evaluate the value delivered by different maintenance techniques. I view maintenance as an operation that moves the turbine to an improved state in which it can generate more power and, thus, earn more revenue. To implement this approach, I model the stochastic deterioration of the turbine in two dimensions: the deterioration rate, and the extent of deterioration, and then use maintenance to improve the state of the turbine. The value of the turbine is the difference between the revenue from to the power generation and the costs incurred in operation and maintenance. With a focus on blade deterioration, I evaluate the value delivered by implementing two different maintenance schemes, predictive maintenance and scheduled maintenance. An example of predictive maintenance technique is the use of Condition Monitoring Systems to precisely detect deterioration. I model Condition Monitoring System (CMS) of different degrees of fidelity, where a higher fidelity CMS would allow the blade state to be determined with a higher precision. The same model is then applied for the scheduled maintenance technique. The improved state information obtained from these techniques is then used to derive an optimal maintenance strategy. The difference between the value of the turbine with and without the inspection type can be interpreted as the value of the inspection. The results indicate that a higher fidelity (and more expensive) inspection method does not necessarily yield the highest value, and, that there is an optimal level of fidelity that results in maximum value. The results also aim to inform the operator of the impact of regional parameters such as wind speed, variance and maintenance costs to the optimal

  11. 14 CFR 119.47 - Maintaining a principal base of operations, main operations base, and main maintenance base...

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Maintaining a principal base of operations, main operations base, and main maintenance base; change of address. 119.47 Section 119.47 Aeronautics... Under Part 121 or Part 135 of This Chapter § 119.47 Maintaining a principal base of operations, main...

  12. Operation and control strategies in pre-series testing of cold circulating pumps for ITER

    International Nuclear Information System (INIS)

    Bhattacharya, R.; Vaghela, H.; Sarkar, B.; Srinivas, M.; Choukekar, K.

    2013-01-01

    Cryo-distribution system of ITER is responsible for the distribution and control of forced-flow supercritical helium for cooling of the superconducting magnets and the cryo-pumps. The requirements of cold circulating pumps (CCP) for mass flow rates and performance are much higher than presently existing and commercially available one used at 4.0 K helium. Design up-scaling with pre-series test of CCP has been proposed including test infrastructure. Operation and control strategies for the test distribution box (TDB) of test infrastructure have been developed and analyzed using steady state and dynamic process simulation to cope with the functional requirements of CCPs. Off-normal scenario with CCP inlet pressure variation is an important concern, dynamic process responses during such scenario have been evaluated to verify the operability of CCP. The paper describes process simulation to cope with the functional requirements of CCPs along with evaluation of off-normal scenario to verify the operability of CCP. (author)

  13. Operation and coupling of LH waves with the ITER-like wall at JET

    International Nuclear Information System (INIS)

    Kirov, K K; Mailloux, J; Arnoux, G; Baranov, Yu; Brix, M; Mayoral, M-L; Rimini, F; Stamp, M; Ekedahl, A; Goniche, M; Petrzilka, V; Jachmich, S; Ongena, J

    2013-01-01

    In this paper important aspects of the lower hybrid (LH) operation with the ITER-like wall (ILW) [1] at JET are reported. Impurity release during LH operation was investigated and it was found that there is no significant Be increase with LH power. The concentration of W was analysed in more detail and it was concluded that LH negligibly contributes to its increase. No cases of W accumulation in LH-only heating experiments were observed so far. LH wave coupling was studied and optimised to achieve the level of system performance similar to before ILW installation. Measurements by Li-beam were used to study systematic dependencies of the scrape-off layer (SOL) density on the gas injection rate from a dedicated gas introduction module and the LH power and launcher position. Experimental results are supported by SOL transport modelling. Observations of arcs in front of the LH launcher and hotspots on magnetically connected sections of the vessel are reported. Overall, a relatively trouble-free operation of the LH system up to 2.5 MW of coupled radio frequency power in L-mode plasma was achieved with no indication that the power cannot be increased further. (paper)

  14. Feasibility study of the cut and weld operations by RH on the cooling pipes of ITER NB components

    Energy Technology Data Exchange (ETDEWEB)

    Pineiro, Oscar; Fernandez, Carlos [TECNATOM Avda. Montes de Oca 28700 S Sebastian de los Reyes, Madrid (Spain); Medrano, Mercedes [EURATOM-CIEMAT Association for Fusion. Avda. Complutense, 22. 28040 Madrid (Spain)], E-mail: mercedes.medrano@ciemat.es; Liniers, Macarena; Botija, Jose; Alonso, Javier; Sarasola, Xabier [EURATOM-CIEMAT Association for Fusion. Avda. Complutense, 22. 28040 Madrid (Spain); Damiani, Carlo [EFDA-Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)

    2009-06-15

    The maintenance operations of ITER NB components inside the vessel - Beam Line Components (BLC's) involve the removal of the faulty component, its transport to the hot cell as well as the reverse operations of transport of the repaired/new component and its reinstallation inside the vessel. Prior to the removal of the BLC's the cooling pipes must be detached from the component following a procedure that applies to the cutting of the pipes and subsequent welding when the component is re-installed. The purpose of this study, conducted in the framework of EFDA, is to demonstrate the feasibility of the cut and weld operations on the water pipes of the BLC's using fully remote handling techniques. Viable technologies for the cut and weld operations have been identified within the study; in particular the following aspects will be presented in the paper: - Different strategies can be pursued in the detachment of the components depending on the number of cut and weld operations to be performed on the pipes. The selected strategy will impact on the procedure to be followed likewise on important aspects as the requirements of the flexible joints assembled on the pipes. - The existing cutting techniques have been examined in the light of the remotely performed pipe cutting at the NB cell. Modifications of commercial tools have been proposed in order to adapt them to the BLC's pipes requirements. The debris produced during the cutting process must be controlled and collected, therefore a cleaning system has been integrated in the adapted cutting tool referred above. - The existing welding techniques have been also examined and compared based on different criteria such as complexity, reliability, alignment tolerances, etc. TIG welding is the preferred technique as it stands out for its superior performance. The commercial tools identified need to be adapted to the NB environment. - The alignment of the pipes is a critical issue concerning the remote welding

  15. Experimental evidence for the suitability of ELMing H-mode operation in ITER with regard to core transport of helium

    International Nuclear Information System (INIS)

    Wade, M.R.; Hillis, D.L.; Burrell, K.H.

    1996-09-01

    Studies have been conducted in DIII-D to assess the viability of the ITER design with regard to helium ash removal, including both global helium exhaust studies and detailed helium transport studies. With respect to helium ash accumulation, the results are encouraging for successful operation of ITER in ELMing H-mode plasmas with conventional high-recycling divertor operation. Helium can be removed from the plasma core with a characteristic time constant of ∼ 8 energy confinement times, even with a central source of helium. Furthermore, the exhaust rate is limited by the pumping efficiency of the system and not by transport of helium within the plasma core. Helium transport studies have shown that D He /X eff ∼ 1 in all confinement regimes studied to date and there is little dependence of D He /X eff on normalized gyroradius in dimensionless scaling studies, suggesting that D He /X eff will be ∼ 1 in ITER. These observations suggest that helium transport within the plasma core should be sufficient to prevent unacceptable fuel dilution in ITER. However, helium exhaust is also strongly dependent on many factors (e.g., divertor plasma conditions, plasma and baffling geometry, flux amplification, pumping speed, etc.) that are difficult to extrapolate. Studies have revealed the helium diffusivity decreases as the plasma density increases, which is unfavorable to ITER's extremely high density operation

  16. Operation and maintenance manual for septic holding tank system for project W-519, two double-wide construction support trailers

    International Nuclear Information System (INIS)

    MORTIMER, C.S.

    1999-01-01

    This manual was prepared to provide detailed information for the operation and maintenance of the sanitary wastewater holding system. It sets forth system operation and maintenance as well as failure response procedures

  17. Application of Risk Monitor MAREas tool in operation and maintenance

    International Nuclear Information System (INIS)

    Carretero, J. A.; Fuentes, I.

    2004-01-01

    From the very beginning and ongoing application objective of the Probabilistic Safety Assessment (PSA) was to develop Monitors. Their development was contingent on the PSA model computing capacity of the computer tools. the availability of effective tools, as well as the requirements of the Consejo de Seguridad Nuclear to apply the Maintenance Rule, have driven their implementation in Spain. The MARE application of Empresarios Agrupados presented herein has been developed for that purpose and has been implemented in Almaraz NPP. This article describes the process followed and experience in using it. (Author)

  18. Mapping Operation and Maintenance Strategy for U.S. Offshore Wind Farms

    Energy Technology Data Exchange (ETDEWEB)

    Dewan, Ashish; Stehly, Tyler

    2017-06-22

    This presentation provides an overview of a collaborative effort between ECN and the National Renewable Energy Laboratory that focused on an operation and maintenance study of six offshore wind power plants in the United States.

  19. Operations and maintenance manual for the water/oil separator (F-2014)

    International Nuclear Information System (INIS)

    Nielsen, R.M.

    1996-01-01

    This Document Provides Operating, Maintenance and Spare Part Information for the Ultra Aqua UFA-6 Water/Oil Separator Installed at MASF. (The plant has been designed for processing of condensates from air compressors.)

  20. Introduction of electronic journal of advanced maintenance website structure and editorial operation

    International Nuclear Information System (INIS)

    Ito, Takashi; Nakamura, Mayu

    2009-01-01

    Electronic Journal of Advanced Maintenance (EJAM) has been issued on the website of Japan Society of Maintenology (JSM) on May 25th, 2009. This report introduces EJAM website structure and Editorial Operation. (author)

  1. Operations and Maintenance Manual for Expanded Bioventing System Site FC-2 Kelly AFB, Texas

    National Research Council Canada - National Science Library

    1996-01-01

    This Operations and Maintenance Manual has been created as a guide for monitoring and maintaining the performance of the bioventing blower and vent well plumbing at the Fire Training Area (Site FC-2...

  2. Point of Maintenance Ruggedized Operational Device Evaluation and Observation Test Report

    National Research Council Canada - National Science Library

    Gorman, Megan

    2002-01-01

    .... The Ruggedized Operational Device Evaluation and Observation (RODEO) test examined hardware packaging, software user interface, and environmental factors associated with the usability of potential Point of Maintenance (POMx) electronic tools...

  3. ITER safety

    International Nuclear Information System (INIS)

    Raeder, J.; Piet, S.; Buende, R.

    1991-01-01

    As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

  4. Ship Operations, Maintenance, Repair and Upgrade for the R/V KILO MOANA

    Science.gov (United States)

    2017-07-20

    From - To) 07/20/2017 Final Technical Report 03/19/2014 to 03/31/2017 4. TITLE AND SUBTITLE Sa. CONTRACT NUMBER Ship Operations, Maintenance , Repair...NUMBER Office of Research Services 2440 Campus Road , Box 368 Honolulu, Hawai’i 96822-2234 9. SPONSORING/MONITORING AGENCY NAME(S) AND ADDRESS(ES) 10...Office of Naval Research. 15. SUBJECT TERMS Research vessel, operation, maintenance , repair. 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF a

  5. A training simulator ensures the competence of operating and maintenance staff

    Energy Technology Data Exchange (ETDEWEB)

    Kaivola, R.; Tamminen, L. [ed.

    1997-11-01

    IVO Generation Services Ltd (IGS) has overall responsibility made on the basis of long-term contracts for the operation and maintenance of the customers` power plants. Partnership is the key concept, and customers are thus able to concentrate on their own specific business activities. Research and development projects are primarily aimed at cutting the customer`s power generation costs and at increasing the efficiency of operation and maintenance

  6. Installation, operation, and maintenance for the pyramidal optics solar system installed at Yacht Cover, Columbia, South Carolina

    Science.gov (United States)

    1980-09-01

    Information concerning the installation, operation, and maintenance of the pyramidal Solar System for space heating and domestic hot water is presented. Principles of operation, sequence of installation, and procedures for the operation and maintenance of each subsystem making up the solar system are presented. Troubleshooting charts and maintenance schedules are presented.

  7. 49 CFR 214.355 - Training and qualification in on-track safety for operators of roadway maintenance machines.

    Science.gov (United States)

    2010-10-01

    ... operators of roadway maintenance machines. 214.355 Section 214.355 Transportation Other Regulations Relating... operators of roadway maintenance machines. (a) The training and qualification of roadway workers who operate roadway maintenance machines shall include, as a minimum: (1) Procedures to prevent a person from being...

  8. Enhanced design, operation and maintenance practices for a longer plant service life

    International Nuclear Information System (INIS)

    Raimondo, E.; Courcoux, A.

    2004-01-01

    Plant service life problems have been under detailed investigation in France and the experience acquired by our company over the past 25 years in the design, construction and maintenance of Pressurized Water Reactors has contributed to develop skills, equipment and capabilities available for efficient plant aging management and component service life extension. The service life of a nuclear power plant is deeply dependant of the provisions made during the design stage, directly linked to good operating conditions and adequate maintenance practices. This paper presents the importance of these three steps (design, operation and maintenance) for plant service life concern. (author)

  9. 49 CFR 195.402 - Procedural manual for operations, maintenance, and emergencies.

    Science.gov (United States)

    2010-10-01

    ... operating conditions by monitoring pressure, temperature, flow or other appropriate operational data and...) Minimization of public exposure to injury and probability of accidental ignition by assisting with evacuation... SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS BY PIPELINE Operation and Maintenance § 195.402 Procedural...

  10. Operation and maintenance of the T-3 cask system

    International Nuclear Information System (INIS)

    Hussey, M.W.; Berger, J.D.; Peterson, J.M.

    1983-01-01

    The T-3 cask system consists of three lead-shielded casks and the associated payload containers, internal fixturing, tiedowns, transportation trailers and handling devices. The three casks were designed to meet the requirements of Title 10 of the Code of Federal Regulations, Part 71. The Nuclear Regulatory Commission cask licensing activities for original design and for licensing revisions have required significant analytical support. Commercial transportation contractors can provide needed services including provisions of suitable equipment, compliances with security requirements, and safe movement of the shipment at a potential savings over DOE-owned transportation systems. Proper periodic inspection/maintenance activities supported by adequate decontamination facilities are a must in keeping the T-3 casks available for service

  11. Magnetic bearings promise reduced operation and maintenance costs

    International Nuclear Information System (INIS)

    Jones, G.

    1990-01-01

    Magnetic bearings are being incorporated into the design of the US DoE modular high temperature gas cooled reactor. The virtually maintenance-free bearing technology may have potential in other nuclear applications. In an active magnetic bearing, a stationary electromagnet (stator) and a rotating ferrous material (rotor) are used to allow a shaft to be suspended in a magnetic field. The position of the shaft is maintained dynamically using position sensors to provide a continuous feedback through a control and amplifier system to the electromagnetic poles which are used to suspend the shaft. Two separate systems are required: an axial positioning system, or thrust bearing, and a pair of radial positioning systems, or journal bearings. (author)

  12. Airbus A320 NEO Base Maintenance Concept SAS Operations

    OpenAIRE

    Dafgård, Oscar

    2017-01-01

    Detta arbete har utförts tillsammans med SAS, för att undersöka om ett base maintenance koncept med ett intervall på 36 månader skulle vara mer kostnadseffektivt än 24 månader för deras nya Airbus A320 NEO flotta. SAS, precis som alla andra flygbolag utnyttjar sina flygplan på sina egna och specifika vis. Eftersom inga flygbolag opererar på samma sätt kan inte heller underhållet skötas på samma sätt för en specifik flygplanstyp. Underhållsprogrammet behövde därför ses över för att optimeras g...

  13. The construction of power grid operation index system considering the risk of maintenance

    Science.gov (United States)

    Tang, Jihong; Wang, Canlin; Jiang, Xinfan; Ye, Jianhui; Pan, Feilai

    2018-02-01

    In recent years, large-scale blackout occurred at home and abroad caused widespread concern about the operation of the grid in the world, and the maintenance risk is an important indicator of grid safety. The barrier operation of the circuit breaker exists in the process of overhaul of the power grid. The operation of the different barrier is of great significance to the change of the power flow, thus affecting the safe operation of the system. Most of the grid operating status evaluation index system did not consider the risk of maintenance, to this end, this paper from the security, economy, quality and cleanliness of the four angles, build the power grid operation index system considering the risk of maintenance.

  14. Education and training of operators and maintenance staff at Hamaoka Nuclear Power Stations

    International Nuclear Information System (INIS)

    Makido, Hideki; Hayashi, Haruhisa

    1999-01-01

    At Hamaoka Nuclear Power Station, in order to ensure higher safety and reliability of plant operation, education and training is provided consistently, on a comprehensive basis, for all operating, maintenance and other technical staff, aimed at developing more capable human resources in the nuclear power division. To this end, Hamaoka Nuclear Power Station has the 'Nuclear Training Center' on its site. The training center provides the technical personnel including operators and maintenance personnel with practical training, utilizing simulators for operation training and the identical facilities with those at the real plant. Thus, it plays a central role in promoting comprehensive education and training concerning nuclear power generation. Our education system covers knowledge and skills necessary for the safe and stable operation of nuclear power plant, targeting new employees to managerial personnel. It is also organized systematically in accordance with experience and job level. We will report the present education and training of operators and maintenance personnel at Hamaoka Nuclear Training Center. (author)

  15. Environmental Management Model for Road Maintenance Operation Involving Community Participation

    Science.gov (United States)

    Triyono, A. R. H.; Setyawan, A.; Sobriyah; Setiono, P.

    2017-07-01

    Public expectations of Central Java, which is very high on demand fulfillment, especially road infrastructure as outlined in the number of complaints and community expectations tweeter, Short Mail Massage (SMS), e-mail and public reports from various media, Highways Department of Central Java province requires development model of environmental management in the implementation of a routine way by involving the community in order to fulfill the conditions of a representative, may serve road users safely and comfortably. This study used survey method with SEM analysis and SWOT with Latent Independent Variable (X), namely; Public Participation in the regulation, development, construction and supervision of road (PSM); Public behavior in the utilization of the road (PMJ) Provincial Road Service (PJP); Safety in the Provincial Road (KJP); Integrated Management System (SMT) and latent dependent variable (Y) routine maintenance of the provincial road that is integrated with the environmental management system and involve the participation of the community (MML). The result showed the implementation of routine maintenance of road conditions in Central Java province has yet to implement an environmental management by involving the community; Therefore developed environmental management model with the results of H1: Community Participation (PSM) has positive influence on the Model of Environmental Management (MML); H2: Behavior Society in Jalan Utilization (PMJ) positive effect on Model Environmental Management (MML); H3: Provincial Road Service (PJP) positive effect on Model Environmental Management (MML); H4: Safety in the Provincial Road (KJP) positive effect on Model Environmental Management (MML); H5: Integrated Management System (SMT) has positive influence on the Model of Environmental Management (MML). From the analysis obtained formulation model describing the relationship / influence of the independent variables PSM, PMJ, PJP, KJP, and SMT on the dependent variable

  16. Reactor operations, inspection and maintenance. PNGS Calibration Program

    International Nuclear Information System (INIS)

    Lopez, E.

    1997-01-01

    The PNGS Calibration Program is being implemented as a response to various concerns identified in recent PEER evaluations and AECB audits. Identified areas of concern were the approach to instrument calibration of Special Safety Systems (SSS). The implementation of a calibration program is a significant improvement in operating practices. A systematic and comprehensive approach to calibration of instrumentation will improve the quality of operation of the plant with a positive contribution to PNGS safety of operation and economic objectives. This paper describes the strategy to implement the proposed calibration program and describes its calibration data requirements. (DM)

  17. Local Fractional Variational Iteration and Decomposition Methods for Wave Equation on Cantor Sets within Local Fractional Operators

    Directory of Open Access Journals (Sweden)

    Dumitru Baleanu

    2014-01-01

    Full Text Available We perform a comparison between the fractional iteration and decomposition methods applied to the wave equation on Cantor set. The operators are taken in the local sense. The results illustrate the significant features of the two methods which are both very effective and straightforward for solving the differential equations with local fractional derivative.

  18. Safety procedures in operation of inspection and maintenance of pressure reduction and metering stations

    International Nuclear Information System (INIS)

    Villas Boas, Ademar Jose; Biesemeyer, Marco Aurelio R.

    2000-01-01

    Each local Natural Gas Distribution Company in Brazil has its own working procedures for operations of inspection and maintenance on equipment and accessories connected to the gas network. Some of these Companies developed a better elaborated and documented way of working routines, while others only work based on their operators experience. The objective of this work is to create a standard procedure for operations of inspection and maintenance of Pressure Reducing Stations and Metering Stations, mainly the ones concerned to safety aspects. This work has no intention of exhausting all aspects related to this subject but to become the first step to standardize these types of operations among Natural Gas Distribution Companies. (author)

  19. Operation and maintenance techniques of pool and pool water purification system in IMEF

    Energy Technology Data Exchange (ETDEWEB)

    Soong, Woong Sup

    1999-03-01

    IMEF pool is used pass way between pool and hot cell in order to inlet and outlet of fuel pin in cask. All operation is performed conforming with naked eyes. Therefore floating matter is filtered so as to easy under water handling. Also radioactivity in pool water is controlled according to the nuclear law, radioactivity ration maintained less than 15mR/hr on pool side. Perfect operation and maintenance can be achieved well trained operator. Result obtained from the perfection can give more influence over restrain, spreading contamination of radioactivity materials. This report describes operation and maintenance technique of pool water purification system in IMEF. (Author). 7 refs., 13 figs.

  20. Operation and maintenance techniques of pool and pool water purification system in IMEF

    International Nuclear Information System (INIS)

    Soong, Woong Sup

    1999-03-01

    IMEF pool is used pass way between pool and hot cell in order to inlet and outlet of fuel pin in cask. All operation is performed conforming with naked eyes. Therefore floating matter is filtered so as to easy under water handling. Also radioactivity in pool water is controlled according to the nuclear law, radioactivity ration maintained less than 15mR/hr on pool side. Perfect operation and maintenance can be achieved well trained operator. Result obtained from the perfection can give more influence over restrain, spreading contamination of radioactivity materials. This report describes operation and maintenance technique of pool water purification system in IMEF. (Author). 7 refs., 13 figs

  1. RA reactor operation and maintenance; Pogon i odrzavanje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air.

  2. Environmental Impacts of Airport Operations: Maintenance, and Expansion

    National Research Council Canada - National Science Library

    Luther, Linda

    2007-01-01

    ... impacts associated with airport operations and expansion are likely to be debated. This issue is important to various stakeholders, particularly those whose health, property values, and quality of life may be affected by such impacts...

  3. AIRCRAFT MAINTENANCE ENABLED JOINT CONCEPT FOR ENTRY OPERATIONS

    Science.gov (United States)

    2017-04-06

    The “off-equipment” AFSs have been reduced as well. Gone are the backshops of Electrical/Environmental, Hydraulics , Avionics, and Armament. The 5th...area (A2/AD) denial battlefronts. While this is a great concept, more must be done to reduce the logistics footprint, improve logistics agility and... reduce costs of logistics operations. Logisticians must always find a way to enable the operations that our Services require. Thesis From the

  4. Development of advanced human-machine system for plant operation and maintenance

    International Nuclear Information System (INIS)

    Wu, Wei; Ohi, Tadashi; Yoshikawa, Hidekazu; Sawaragi, Tetsuo; Kitamura, Masaharu; Furuta, Kazuo; Gofuku, Akio; Ito, Koji

    2004-01-01

    With the worldwide deregulation of the power industry, and the aging of the nuclear power plants (NPPs), concerns are growing over the reliability and safety of the NPPs, because the regulation of man power may lower the current high level of reliability and safety. In this paper, a concept of overall integrated plant management mechanism is proposed, in order to meet the requirements of cutting costs of NPPs and the requirements of maintaining or increasing safety and reliability. The concept is called as satellite operation maintenance center (SOMC). SOMC integrates the operation and maintenance activities of several NPP units by utilizing advanced information technologies to support cooperation activities between workers allocated at SOMC and the field workers. As for the operation activities, a framework called as Advanced Operation System (AOS) is proposed in this paper. AOS consists of three support sub-systems: dynamic operation permission system(DyOPS), supervisor information presentation system using interface agent, and crew performance evaluation system. As for the maintenance activities, a framework called as Ubiquitous-Computing-based Maintenance support System (UCMS) is proposed next. Two case studies are described, in order to show the way of how UCMS support field workers to do maintenance tasks efficiently, safely, and infallibly as well. Finally, a prospect of SOMC is shown in order to explain the way of how the technology elements developed in this project could be integrated as a whole one system to support maintenance activities of NPPs in the future. (author)

  5. ICRF heating in JET during initial operations with the ITER-like wall

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet, P.; Brix, M.; Graham, M.; Mayoral, M.-L.; Meigs, A.; Monakhov, I.; Sirinelli, A. [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Bobkov, V.; Drewelow, P.; Pütterich, T. [Max-Planck-Institut für Plasmaphysik, EURATOM-Assoziation, Garching (Germany); Brezinsek, S. [IEK-4, Forschungszentrum Jülich, Association EURATOM-FZJ (Germany); Campergue, A-L. [Ecole Nationale des Ponts et Chaussées, F77455 Marne-la-Vallée (France); Colas, L. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Czarnecka, A. [Association Euratom-IPPLM, Hery 23, 01-497 Warsaw (Poland); Klepper, C. C. [Oak Ridge National Laboratory, Oak Ridge, TN 37831-6169 (United States); Lerche, E.; Van-Eester, D. [Association EURATOM-Belgian State, ERM-KMS, Brussels (Belgium); Milanesio, D. [Politecnico di Torino, Department of Electronics, Torino (Italy); Mlynar, J. [Association EURATOM-IPP.CR, Za Slovankou 3, 182 21 Praha 8 (Czech Republic); Collaboration: JET-EFDA Contributors

    2014-02-12

    In 2011/12, JET started operation with its new ITER-Like Wall (ILW) made of a tungsten (W) divertor and a beryllium (Be) main chamber wall. The impact of the new wall material on the JET Ion Cyclotron Resonance Frequency (ICRF) operation was assessed and also the properties of JET plasmas heated with ICRF were studied. No substantial change of the antenna coupling resistance was observed with the ILW as compared with the carbon wall. Heat-fluxes on the protecting limiters close the antennas quantified using Infra-Red (IR) thermography (maximum 4.5 MW/m{sup 2} in current drive phasing) are within the wall power load handling capabilities. A simple RF sheath rectification model using the antenna near-fields calculated with the TOPICA code can well reproduce the heat-flux pattern around the antennas. ICRF heating results in larger tungsten and nickel (Ni) contents in the plasma and in a larger core radiation when compared to Neutral Beam Injection (NBI) heating. Some experimental facts indicate that main-chamber W components could be an important impurity source: the divertor W influx deduced from spectroscopy is comparable when using RF or NBI at same power and comparable divertor conditions; the W content is also increased in ICRF-heated limiter plasmas; and Be evaporation in the main chamber results in a strong and long lasting reduction of the impurity level. The ICRF specific high-Z impurity content decreased when operating at higher plasma density and when increasing the hydrogen concentration from 5% to 20%. Despite the higher plasma bulk radiation, ICRF exhibited overall good plasma heating efficiency; The ICRF power can be deposited at plasma centre and the radiation is mainly from the outer part of the plasma. Application of ICRF heating in H-mode plasmas started, and the beneficial effect of ICRF central electron heating to prevent W accumulation in the plasma core could be observed.

  6. Operation and maintenance manual of the accelerator installed in the facility of radiation standards

    International Nuclear Information System (INIS)

    Fujii, Katsutoshi; Kawasaki, Katsuya; Kowatari, Munehiko; Tanimura, Yoshihiko; Kajimoto, Yoichi; Shimizu, Shigeru

    2006-08-01

    4MV Van de Graff accelerator was installed in the Facility of Radiation Standards (FRS) in June 2000, and monoenergetic neutron calibration fields and high energy γ-ray calibration fields have been developed. The calibration fields are provided for R and D on dosimetry, and for the calibration and type-test of radiation protection instruments. This article describes the operational procedure, the maintenance work and the operation of the related apparatuses of the accelerator. This article focuses on the sufficient safety and radiation control for the operators, the maintenance performance of the accelerator, and on the prevention of the malfunction due to the mistakes of the operators. This article targets the unexperienced engineers in charge of operation and maintenance of the accelerator. (author)

  7. Intelligent Operation and Maintenance of Micro-grid Technology and System Development

    Science.gov (United States)

    Fu, Ming; Song, Jinyan; Zhao, Jingtao; Du, Jian

    2018-01-01

    In order to achieve the micro-grid operation and management, Studying the micro-grid operation and maintenance knowledge base. Based on the advanced Petri net theory, the fault diagnosis model of micro-grid is established, and the intelligent diagnosis and analysis method of micro-grid fault is put forward. Based on the technology, the functional system and architecture of the intelligent operation and maintenance system of micro-grid are studied, and the microcomputer fault diagnosis function is introduced in detail. Finally, the system is deployed based on the micro-grid of a park, and the micro-grid fault diagnosis and analysis is carried out based on the micro-grid operation. The system operation and maintenance function interface is displayed, which verifies the correctness and reliability of the system.

  8. Operation and maintenance of thermal power stations best practices and health monitoring

    CERN Document Server

    Chanda, Pradip

    2016-01-01

    This book illustrates operation and maintenance practices/guidelines for economic generation and managing health of a thermal power generator beyond its regulatory life. The book provides knowledge for professionals managing power station operations, through its unique approach to chemical analysis of water, steam, oil etc. to identify malfunctioning/defects in equipment/systems much before the physical manifestation of the problem. The book also contains a detailed procedure for conducting performance evaluation tests on different equipment, and for analyzing test results for predicting maintenance requirements, which has lent a new dimension to power systems operation and maintenance practices. A number of real life case studies also enrich the book. This book will prove particularly useful to power systems operations professionals in the developing economies, and also to researchers and students involved in studying power systems operations and control. .

  9. Operations and maintenance of the Gasunie Transportation System

    Energy Technology Data Exchange (ETDEWEB)

    Panman, Bert

    1999-07-01

    Gasunie is a one-of-a-kind company in the Netherlands. It has been trading and transmitting of natural gas since the 1960's. The company has a dominant position: 90% market share in the Netherlands and 23% in Western Europe. This presentation introduces the company and describes its 11,398 km long grid system, with compressor stations, blending stations, metering and regulation stations, gas delivery stations, export stations, storage of LNG, calibration systems and nitrogen plant. Gasunie experiences a changing environment characterized by liberalization of the gas market and technological development. The response of the company to this changing environment is overviewed. In addition to revising the commercial strategy, Gasunie continuously tries to cut costs by enabling information technology (IT), reduction of staff and other organizational changes, benchmarking, scrutinizing maintenance policies, and smart purchasing of goods and services. These efforts are discussed in turn. Finally, the implementation of SAP R/3 is discussed. SAP R/3 is SAP's integrated software solution for Client/Server and Distributed Open Systems.

  10. The remote handling systems for ITER

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Isabel, E-mail: mir@isr.ist.utl.pt [Institute for Systems and Robotics/Instituto Superior Tecnico, Lisboa (Portugal); Damiani, Carlo [Fusion for Energy, Barcelona (Spain); Tesini, Alessandro [ITER Organization, Cadarache (France); Kakudate, Satoshi [ITER Tokamak Device Group, Japan Atomic Energy Agency, Ibaraki (Japan); Siuko, Mikko [VTT Systems Engineering, Tampere (Finland); Neri, Carlo [Associazione EURATOM ENEA, Frascati (Italy)

    2011-10-15

    The ITER remote handling (RH) maintenance system is a key component in ITER operation both for scheduled maintenance and for unexpected situations. It is a complex collection and integration of numerous systems, each one at its turn being the integration of diverse technologies into a coherent, space constrained, nuclearised design. This paper presents an integrated view and recent results related to the Blanket RH System, the Divertor RH System, the Transfer Cask System (TCS), the In-Vessel Viewing System, the Neutral Beam Cell RH System, the Hot Cell RH and the Multi-Purpose Deployment System.

  11. Designing nuclear power plants for improved operation and maintenance

    International Nuclear Information System (INIS)

    1996-09-01

    The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig

  12. Designing nuclear power plants for improved operation and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig.

  13. Heating, current drive and energetic particles studies on JET in preparation of ITER operation

    International Nuclear Information System (INIS)

    Noterdaeme, J.-M.; Budny, R.; Cardinali, A.

    2003-01-01

    This paper summarizes the recent work on JET in the three areas of heating, current drive and energetic particles. The achievements have extended the possibilities of JET, have a direct connection to ITER operation and provide new and interesting physics. Toroidal rotation profiles of plasmas heated far off axis with little or no refueling or momentum input are hollow with only small differences on whether the power deposition is located on the low field side or on the high field side. With LH current drive the magnetic shear was varied from slightly positive to negative. The improved coupling (through the use of plasma shaping and CD 4 ) allowed up to 3.4 MW of P LH in ITB plasmas with more than 15MW of combined NBI and ICRF heating. The q profile with negative magnetic shear and the ITB could be maintained for the duration of the high heating pulse (8s). Fast ions have been produced in JET with ICRF to simulate alpha particles: by using third harmonic 4 He heating, beam injected 4 He at 120 kV were accelerated to energies above 2 MeV, taking advantage of the unique capability of JET to use NBI with 4 He and to confine MeV class ions. ICRF heating was used to replicate the dynamics of alpha heating and the control of an equivalent Q=10 'burn' was simulated. (author)

  14. TMI cable tracer operation and maintenance manual for assembly 417910

    International Nuclear Information System (INIS)

    Sumstine, R.L.

    1983-11-01

    This manual provides technical information and instructions to operate and maintain the cable tracer designed for the Three Mile Island (TMI) Unit 2 Reactor Building. The TMI cable tracer was developed to allow TMI personnel to trace cables in cable trays that may be tested or sectioned for destructive examination

  15. RA reactor operation and maintenance in 1989, Part 1

    International Nuclear Information System (INIS)

    Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Zivotic, Z.; Majstorovic, D.; Sanovic, V.

    1989-01-01

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in July 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The following major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the power supply system. Project concerned with renewal of RA reactor complete instrumentation was started at the end of 1988. Contract was signed between the IAEA and Soviet Atomenergoexport for supplying the new instrumentation for the RA reactor. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988. In 1989, device for water purification designed by the reactor staff started operation and spent fuel handling equipment is being mounted. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor [sr

  16. RA reactor operation and maintenance, Annual report 1974

    International Nuclear Information System (INIS)

    Milosevic, D. et al

    1974-12-01

    During 1974, RA reactor was operated at nominal power for 194 days and 13 days at lower power levels. The total production was 30711 MWh which is 2.4% higher than planned. Practically there were no discrepancies from the plan. The reactor was used for irradiation and experiments according to the demand of 437 users. This report contains detailed data about reactor power and experiments performed in 1974. Total number of afety shutdowns was 11, of which 8 were caused by power cuts, and 3 due to human error. Maximum individual personnel exposure dose was 50% of the maximum permissible dose. There were no accidents during this year. Decontamination of surfaces was less than during previous years. About 805 m 2 of surfaces and 178 objects were decontaminated. It was concluded that the successful operation in 1974 has a special significance taking into account the financial problems [sr

  17. Decision support for operations and maintenance (DSOM) system

    Science.gov (United States)

    Jarrell, Donald B [Kennewick, WA; Meador, Richard J [Richland, WA; Sisk, Daniel R [Richland, WA; Hatley, Darrel D [Kennewick, WA; Brown, Daryl R [Richland, WA; Keibel, Gary R [Richland, WA; Gowri, Krishnan [Richland, WA; Reyes-Spindola, Jorge F [Richland, WA; Adams, Kevin J [San Bruno, CA; Yates, Kenneth R [Lake Oswego, OR; Eschbach, Elizabeth J [Fort Collins, CO; Stratton, Rex C [Richland, WA

    2006-03-21

    A method for minimizing the life cycle cost of processes such as heating a building. The method utilizes sensors to monitor various pieces of equipment used in the process, for example, boilers, turbines, and the like. The method then performs the steps of identifying a set optimal operating conditions for the process, identifying and measuring parameters necessary to characterize the actual operating condition of the process, validating data generated by measuring those parameters, characterizing the actual condition of the process, identifying an optimal condition corresponding to the actual condition, comparing said optimal condition with the actual condition and identifying variances between the two, and drawing from a set of pre-defined algorithms created using best engineering practices, an explanation of at least one likely source and at least one recommended remedial action for selected variances, and providing said explanation as an output to at least one user.

  18. Design and operation of remote maintenance systems in JET

    International Nuclear Information System (INIS)

    Raimondi, T.

    1987-01-01

    The JET tokamak is a joint European project aimed at proving the viability of nuclear fusion as a source of energy. A remote handling system is being developed for this large experimental facility. Force feedback servomanipulators and TV cameras are positioned at work locations by large transporters. Positioning and tele-operation are computer-assisted. Special tools are being devised to facilitate difficult tasks

  19. Operations and maintenance manual for the linear accelerator (sled)

    Science.gov (United States)

    1981-01-01

    The Linear Accelerator, a sliding chair which is pulled along a stationary platform in a horizontal axis is described. The driving force is a motor controlled by a velocity loop amplifier, and the mechanical link to the chair is a steel cable. The chair is moved in forward and reverse directions as indicated by the direction of motor rotation. The system operation is described with emphasis on the electronic control and monitoring functions. Line-by-line schematics and wire lists are included.

  20. Education and training of operators and maintenance staff at commercial nuclear power stations in Japan

    International Nuclear Information System (INIS)

    Takahashi, M.; Kataoka, H.

    1998-01-01

    Safe and stable operation of a nuclear power station requires personnel fostering. In Japan, with the objectives of systematically securing qualified people for a long period of time, and maintaining and improving their skills and knowledge, the utilities have created strict personnel training plans, for continuous education and training. Concrete examples of education and training for operators and maintenance personnel at commercial nuclear power stations in Japan, such as education systems training, facility and contents of curriculum, are detailed including some related matters. Recent activities to catch up with environment changes surrounding education and training of operators and maintenance staff are also mentioned. (author)

  1. 40 CFR 63.7335 - How do I demonstrate continuous compliance with the operation and maintenance requirements that...

    Science.gov (United States)

    2010-07-01

    ... corrective action is completed. (c) To demonstrate continuous compliance with the operation and maintenance... compliance with the operation and maintenance requirements that apply to me? 63.7335 Section 63.7335... maintenance requirements that apply to me? (a) For each by-product coke oven battery, you must demonstrate...

  2. 40 CFR 63.7826 - How do I demonstrate initial compliance with the operation and maintenance requirements that...

    Science.gov (United States)

    2010-07-01

    ... preventative maintenance schedule and, as applicable, detailed descriptions of the corrective action procedures... compliance with the operation and maintenance requirements that apply to me? 63.7826 Section 63.7826... Compliance Requirements § 63.7826 How do I demonstrate initial compliance with the operation and maintenance...

  3. 25 CFR 39.1201 - Establishment of an interim fiscal year 1980 operation and maintenance fund for contract schools.

    Science.gov (United States)

    2010-04-01

    ... and maintenance fund for contract schools. 39.1201 Section 39.1201 Indians BUREAU OF INDIAN AFFAIRS... the Contract School Operation and Maintenance Fund. The Secretary shall cause the distribution of an... an appropriate account or subaccount for the Contract School Operation and Maintenance Fund. ...

  4. Influence of visual feedback on human task performance in ITER remote handling

    NARCIS (Netherlands)

    Schropp, Gwendolijn Y R; Heemskerk, Cock J M; Kappers, Astrid M L; Bergmann Tiest, Wouter M; Elzendoorn, Ben S Q; Bult, David

    In ITER, maintenance operations will be largely performed by remote handling (RH). Before ITER can be put into operation, safety regulations and licensing authorities require proof of maintainability for critical components. Part of the proof will come from using standard components and procedures.

  5. Computer-aided acquisition and logistics support (CALS): Concept of Operations for Depot Maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Bourgeois, N.C.; Greer, D.K.

    1993-04-01

    This CALS Concept of Operations for Depot Maintenance provides the foundation strategy and the near term tactical plan for CALS implementation in the depot maintenance environment. The user requirements enumerated and the overarching architecture outlined serve as the primary framework for implementation planning. The seamless integration of depot maintenance business processes and supporting information systems with the emerging global CALS environment will be critical to the efficient realization of depot user's information requirements, and as, such will be a fundamental theme in depot implementations.

  6. 40 CFR 63.7710 - What are my operation and maintenance requirements?

    Science.gov (United States)

    2010-07-01

    ... defect or deficiency as soon as practicable. (2) Operating limits for each capture system for an... 40 Protection of Environment 13 2010-07-01 2010-07-01 false What are my operation and maintenance requirements? 63.7710 Section 63.7710 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR...

  7. Reliability and risk-based planning of operation and maintenance of offshore wind turbines

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Florian, Mihai; Berzonskis, Arvydas

    2016-01-01

    costly (and safe), and it is important to include in the reliability assessment the information obtained during operation (from condition monitoring and inspections) and the maintenance performed (incl. repairs and replacements). The paper presents a risk-based approach for optimal planning of Operation...

  8. 75 FR 62469 - Drawbridge Operation Regulations; Charles River, Boston, MA, Maintenance

    Science.gov (United States)

    2010-10-12

    ... Operation Regulations; Charles River, Boston, MA, Maintenance AGENCY: Coast Guard, DHS. ACTION: Notice of... Craigie Bridge across the Charles River at mile 1.0, has a vertical clearance of 10.25 feet at normal pool... temporary deviation from the regulation governing the operation of the Craigie Bridge across the Charles...

  9. Landfill gas operation and maintenance manual of practice

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This manual has the following objectives: (1) compile and present key portions of the general body of knowledge about operating and maintaining LFG control systems; (2) present information in an easy to understand format useful for hands-on practical use in the field; (3) present accepted practices and procedures for LFG control practices; (4) highlight key points, common mistakes and lessons learned from more than 20 years of industry experience, point out areas of controversy and indicate alternative practices where applicable; (5) compile key reference information; and (6) provide theory and discussion needed to develop a deeper understanding of LFG control and recovery.

  10. RA Research reactor, Annual report 1970 - Operation and maintenance

    International Nuclear Information System (INIS)

    Milosevic, D. et al.

    1970-12-01

    During 1970, the RA Reactor was operated at nominal power of 6.5 MW for 160 days, and 40 days at lower power levels. Total production mounted to 25968 MWh which is 3.87% higher than planned. The action plan was changed compared to the previous years because of sending the heavy water to France for re-concentration. Isotopic concentration of the heavy water was decreased to 99.05% and now after re-concentration it is 99.96%. Discrepancy from the action plan, in September was caused by the delay return of the heavy water for administrative and transportation difficulties. The restart of the reactor in September was postponed because the cladding of one fuel element was damaged immediately after the start-up, and the reactor had to be shutdown. In October and November reactor was in operation 28 and 25 days respectively which enabled to make up for the lost time. Reactor was used for irradiation and experiments according to the demand of 390 users, 340 from the Institute and 50 external users. This report contains detailed data about reactor power and experiments performed in 1969. It is concluded that the reactor operated successfully according to the plan. Shorter interruptions were caused only by difficulties with water supply pipes and sliding of the soil. Reactor was only twice scram shutdown because of the false signals caused by failures of the electronic control instrumentation. the period when reactor was not in operation was used for inspection of the reactor vessel internals. By using special TV cameras and telescopes, it was found that the there are no signs of corrosion on the reactor vessel, e.e. that the internals are in a very good state. Simultaneously, connection for the pipes of future emergency core cooling system were constructed. During 1970, the spent fuel was repacked from fuel channels into special aluminium casks. Four casks containing 660 fuel slugs was deposited int the storage pool No.4. There is now 18 casks with 2951 spent fuel slugs in

  11. RF-source development for ITER: Large area H- beam extraction, modifications for long pulse operation and design of a half size ITER source

    International Nuclear Information System (INIS)

    Kraus, W.; Heinemann, B.; Falter, H.D.; Franzen, P.; Speth, E.; Entscheva, A.; Fantz, U.; Franke, T.; Holtum, D.; Martens, Ch.; McNeely, P.; Riedl, R.; Wilhelm, R.

    2005-01-01

    With an extraction area of 152 cm 2 a calorimetrically measured H - current density of 19.3 mA/cm 2 has been achieved at 0.45 Pa with 90 kW RF power. With 306 cm 2 the electrically measured H - current has reached up to 9.7 A corresponding to 32 mA/cm 2 at 100 kW. The current on the calorimeter is limited by the extraction system. Down to 0.2 Pa only a weak dependence on the source pressure has been observed. The test bed will be upgraded to demonstrate cw operation with deuterium. Based on the tested prototype a half size ITER RF-source of 80 cm x 90 cm with 360 kW RF power has been designed

  12. ITER overview

    International Nuclear Information System (INIS)

    Shimomura, Y.; Aymar, R.; Chuyanov, V.; Huguet, M.; Parker, R.R.

    2001-01-01

    This report summarizes technical works of six years done by the ITER Joint Central Team and Home Teams under terms of Agreement of the ITER Engineering Design Activities. The major products are as follows: complete and detailed engineering design with supporting assessments, industrial-based cost estimates and schedule, non-site specific comprehensive safety and environmental assessment, and technology R and D to validate and qualify design including proof of technologies and industrial manufacture and testing of full size or scalable models of key components. The ITER design is at an advanced stage of maturity and contains sufficient technical information for a construction decision. The operation of ITER will demonstrate the availability of a new energy source, fusion. (author)

  13. ITER Overview

    International Nuclear Information System (INIS)

    Shimomura, Y.; Aymar, R.; Chuyanov, V.; Huguet, M.; Parker, R.

    1999-01-01

    This report summarizes technical works of six years done by the ITER Joint Central Team and Home Teams under terms of Agreement of the ITER Engineering Design Activities. The major products are as follows: complete and detailed engineering design with supporting assessments, industrial-based cost estimates and schedule, non-site specific comprehensive safety and environmental assessment, and technology R and D to validate and qualify design including proof of technologies and industrial manufacture and testing of full size or scalable models of key components. The ITER design is at an advanced stage of maturity and contains sufficient technical information for a construction decision. The operation of ITER will demonstrate the availability of a new energy source, fusion. (author)

  14. Standard Hydrogen Monitoring System-C operation and maintenance manual

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1997-01-01

    The primary function of the SHMS-C is to monitor specifically for hydrogen in the waste tank vapor space which may also contain (but not be limited to) unknown quantities of air, nitrous oxide (N 2 O), ammonia (NH 3 ), water vapor, carbon dioxide (CO 2 ), carbon monoxide (CO) and other gaseous constituents. An electronically controlled grab sampler has replaced the manually operated sample system that was used in the original SHMS enclosure. Samples can now be operator or automatically initiated. Automatic initiation occurs based on the high hydrogen alarm level. Once a sample is obtained it is removed from the sampler and transported to a laboratory for analysis. This system is used to identify other gaseous constituents which are not measured by the hydrogen monitor. The design does not include any remote data acquisition or remote data logging equipment but provides a 4--20 mA dc process signals, and discrete alarm contacts, that can be utilized for remote data logging and alarming when desired. The SHMS-C arrangement consists of design modifications (piping, valves, filters, supports) to the SHMS-B arrangement necessary for the installation of a dual column gas chromatograph and associated sample and calibration gas lines. The gas chromatograph will provide real time, analytical quality, specific hydrogen measurements in low and medium range concentrations. The system is designed to sample process gases that are classified by NEC code as Class 1, Division 1, Group B

  15. The radioactive materials packaging handbook: Design, operations, and maintenance

    International Nuclear Information System (INIS)

    Shappert, L.B.; Bowman, S.M.; Arnold, E.D.

    1998-01-01

    As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE's cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials

  16. The radioactive materials packaging handbook: Design, operations, and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

    1998-08-01

    As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

  17. Artificial Intelligent Platform as Decision Tool for Asset Management, Operations and Maintenance.

    Science.gov (United States)

    2018-01-04

    An Artificial Intelligence (AI) system has been developed and implemented for water, wastewater and reuse plants to improve management of sensors, short and long term maintenance plans, asset and investment management plans. It is based on an integrated approach to capture data from different computer systems and files. It adds a layer of intelligence to the data. It serves as a repository of key current and future operations and maintenance conditions that a plant needs have knowledge of. With this information, it is able to simulate the configuration of processes and assets for those conditions to improve or optimize operations, maintenance and asset management, using the IViewOps (Intelligent View of Operations) model. Based on the optimization through model runs, it is able to create output files that can feed data to other systems and inform the staff regarding optimal solutions to the conditions experienced or anticipated in the future.

  18. Design of an operator support system for online maintenance at nuclear power plant

    International Nuclear Information System (INIS)

    Chu Yongyue; Li Huwei; Gao Qiang; Yi Yan; Yang Ming

    2013-01-01

    Online maintenance based on reliability centered management is pivotal for the safe and economical operation of Nuclear Power Plant (NPP). This paper presents an operator support system through which the operators can effectively manage plant configuration and identify the weaknesses in plant operation. The proposed operator support system is based on the GO-FLOW, which is a success-oriented availability analysis methodology and can be used for evaluating phased missions. In this paper, the design of the proposed operator support system is introduced through a case study of the Auxiliary Feed Water System (AFWS). (author)

  19. Operation and maintenance of the RA reactor in 1965

    International Nuclear Information System (INIS)

    Milosevic, D.

    1966-01-01

    It has been planned for 1965 that the RA reactor would be operated each month for 20 days at nominal power of 6.5 MW, at lower power for 5 days, meaning production of 27 400 MWh. The plan was fulfilled since reactor produced 28809 MWh, i.e. 5% more than planned. Reactor was used for irradiation in the vertical experimental channels according to the demand of 1264 users from the Institute and 191 external users. Two groups of experiments done: at nominal power simultaneously with isotope production and experiments which demanded particular power levels and temperatures. Three fuel exchanges were done during this year, meaning that 40 fuel channels were changed in total. Vertical experimental channels VEK-1 and VEK-9 having diameter 100 mm were changed by channels having diameter 50 mm and shortened by 435 mm. Channel VEK-5 with diameter 110 mm was changed shortened by 430 mm. This enabled better fuel economy, the burnup was increased from 4500 MWd/t to 5000 MWd/t. This report contains the action plan for 1966

  20. ITER council proceedings: 1998

    International Nuclear Information System (INIS)

    1999-01-01

    This volume contains documents of the 13th and the 14th ITER council meeting as well as of the 1st extraordinary ITER council meeting. Documents of the ITER meetings held in Vienna and Yokohama during 1998 are also included. The contents include an outline of the ITER objectives, the ITER parameters and design overview as well as operating scenarios and plasma performance. Furthermore, design features, safety and environmental characteristics are given

  1. Advanced maintenance strategies for power plant operators--introducing inter-plant life cycle management

    International Nuclear Information System (INIS)

    Graeber, Ulrich

    2004-01-01

    One of the most important goals of competing power plant operators is to ensure safe operation of their plants, characterized by maximum availability throughout the entire life cycle and minimized specific generating costs. One parameter crucial to the total price of electricity--and one that can be actively influenced by the power plant operators--is maintenance. Up to 30% of all electricity generating costs accrue from maintenance. In the past years maintenance measures have been optimized particularly by the application and continuing development of testing and diagnostic techniques, by the increased level of system and component automation as well as more efficient organization structures. Despite the considerable success of these efforts, the potential for further cost reductions is still far from exhausted. But the risks connected to reliability, availability and safety need to be analyzed in greater detail in order to ensure the sustainability of the savings already achieved as well as those yet to be realized. The systematic application of condition-based maintenance and the implementation of structured life cycle management are essential requirements. An inter-plant approach is recommended to make a quick implementation of maintenance optimization potentials possible. Plant-specific improvement potentials can be established with the help of a best-practice comparison, and measures and priorities can be defined for realizing them. Creating an inter-plant database will allow experience and findings to be analyzed quickly and efficiently by experts and made available to all participants on a neutral platform. Despite--or maybe owing to--the increasingly competitive marketplace, a sustained reduction in the maintenance costs of power plant operators can only be achieved through a structured, inter-plant exchange of experience. The ZES offers the industry a suitable platform for cooperation with its 'Condition-Based Maintenance' research focus. The introduction

  2. Tackling the knowledge needs of maintenance and operation staff in mouldy housing

    DEFF Research Database (Denmark)

    Bonderup, Sirid; Gunnarsen, Lars Bo

    2017-01-01

    Interdisciplinary collaboration is key when it comes to solving and preventing mould problems in housing. Many forms of collaboration is necessary, not just between operating staff, inhabitants, management and tradespersons, but also knowing and working with the building structure in question...... discussed how a digital tool could help operating staff gather, share and systematise knowledge of local conditions and practices in order to improve operation and maintenance....

  3. Centralized operations and maintenance planning at the Atacama Large Millimeter/submillimeter Array (ALMA)

    Science.gov (United States)

    Lopez, Bernhard; Whyborn, Nicholas D.; Guniat, Serge; Hernandez, Octavio; Gairing, Stefan

    2016-07-01

    The Atacama Large Millimeter/submillimeter Array (ALMA) is a joint project between astronomical organizations in Europe, North America, and East Asia, in collaboration with the Republic of Chile. ALMA consists of 54 twelve-meter antennas and 12 seven-meter antennas operating as an aperture synthesis array in the (sub)millimeter wavelength range. Since the inauguration of the observatory back in March 2013 there has been a continuous effort to establish solid operations processes for effective and efficient management of technical and administrative tasks on site. Here a key aspect had been the centralized maintenance and operations planning: input is collected from science stakeholders, the computerized maintenance management system (CMMS) and from the technical teams spread around the world, then this information is analyzed and consolidated based on the established maintenance strategy, the observatory long-term plan and the short-term priorities definitions. This paper presents the high-level process that has been developed for the planning and scheduling of planned- and unplanned maintenance tasks, and for site operations like the telescope array reconfiguration campaigns. We focus on the centralized planning approach by presenting its genesis, its current implementation for the observatory operations including related planning products, and we explore the necessary next steps in order to fully achieve a comprehensive centralized planning approach for ALMA in steady-state operations.

  4. Research Project 'RB research nuclear reactor' (operation and maintenance), Final report

    International Nuclear Information System (INIS)

    1985-01-01

    This final report covers operation and maintenance activities at the RB reactor during period from 1981-1985. First part covers the RB reactor operation, detailed description of reactor components, fuel, heavy water, reactor vessel, cooling system, equipment and instrumentation, auxiliary systems. It contains data concerned with dosimetry and radiation protection, reactor staff, and financial data. Second part deals maintenance, regular control and testing of reactor equipment and instrumentation. Third part is devoted to basic experimental options and utilization of the RB reactor including training

  5. Procedure for estimating nonfuel operation and maintenance costs for large steam-electric power plants

    International Nuclear Information System (INIS)

    Myers, M.L.; Fuller, L.C.

    1979-01-01

    Revised guidelines are presented for estimating annual nonfuel operation and maintenance costs for large steam-electric power plants, specifically light-water-reactor plants and coal-fired plants. Previous guidelines were published in October 1975 in ERDA 76-37, a Procedure for Estimating Nonfuel Operating and Maintenance Costs for Large Steam-Electric Power Plants. Estimates for coal-fired plants include the option of limestone slurry scrubbing for flue gas desulfurization. A computer program, OMCOST, is also presented which covers all plant options

  6. Technical requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

  7. Proposal for the award of a contract for the maintenance and operation of CERN's sewage installations

    CERN Document Server

    2006-01-01

    This document concerns the award of a contract for the maintenance and operation of CERN's sewage installations. The Finance Committee is invited to agree to the negotiation of a contract with VALLIER ASSAINISSEMENT (FR), the lowest bidder, for the maintenance and operation of CERN's sewage installations for a period of three years for a total amount of 1 745 897 Swiss francs, not subject to revision. The contract will include options for two one-year extensions beyond the initial three-year period.

  8. Outsourcing strategy and tendering methodology for the operation and maintenance of CERN’s cryogenic facilities

    Science.gov (United States)

    Serio, L.; Bremer, J.; Claudet, S.; Delikaris, D.; Ferlin, G.; Ferrand, F.; Pezzetti, M.; Pirotte, O.

    2017-12-01

    CERN operates and maintains the world largest cryogenic infrastructure ranging from ageing but well maintained installations feeding detectors, test facilities and general services, to the state-of-the-art cryogenic system serving the flagship LHC machine complex. A study was conducted and a methodology proposed to outsource to industry the operation and maintenance of the whole cryogenic infrastructure. The cryogenic installations coupled to non LHC-detectors, test facilities and general services infrastructure have been fully outsourced for operation and maintenance on the basis of performance obligations. The contractor is responsible for the operational performance of the installations based on a yearly operation schedule provided by CERN. The maintenance of the cryogenic system serving the LHC machine and its detectors has been outsourced on the basis of tasks oriented obligations, monitored by key performance indicators. CERN operation team, with the support of the contractor operation team, remains responsible for the operational strategy and performances. We report the analysis, strategy, definition of the requirements and technical specifications as well as the achieved technical and economic performances after one year of operation.

  9. Numerical investigation of collector cooling for a 1 MW ITER gyrotron operated with vertical sweeping

    Energy Technology Data Exchange (ETDEWEB)

    Savoldi, Laura; Bertani, Cristina [Dipartimento Energia, Politecnico di Torino (Italy); Cau, Francesca; Cismondi, Fabio [Fusion for Energy, Barcelona (Spain); Gantenbein, Gerd; Illy, Stefan [KIT, Karlsruhe (Germany); Monni, Grazia [Dipartimento Energia, Politecnico di Torino (Italy); Zanino, Roberto, E-mail: roberto.zanino@polito.it [Dipartimento Energia, Politecnico di Torino (Italy)

    2015-11-15

    The present gyrotron designs for EC plasma heating in nuclear fusion reactors require the safe exhaust of a power comparable to that injected into the plasma, in order to keep the maximum temperature below the acceptable value of 300 °C. In this paper, the commercial computational fluid dynamics (CFD) software STAR-CCM+{sup ®} is used to analyze the thermal performance of the annular copper collector of a 1 MW ITER gyrotron, equipped with a hypervapotron structure made of annular fins with rectangular cavities of aspect ratio (depth/width) = 3, cooled by highly subcooled (90–100 °C) pressurized water flowing at ∼4 m/s. It is assumed that the simple vertical sweeping strategy is used to reduce the very high peak heat flux on the collector (up to 30 MW/m{sup 2} transient, 5 MW/m{sup 2} time average), due to the spent electron beam. The 2D steady-state conjugate heat transfer problem is solved assuming azimuthal symmetry and accounting for 2-phase flow. The single-cavity flow and heat transfer problem is considered first, to optimize the mesh and the selection of the turbulence model. For the operating conditions considered in this paper, the full collector (100+ cavities) solution shows that boiling occurs only in a limited number of cavities close to the peaks of the heat flux, with the vapor remaining trapped in the bottom of the cavities, i.e. no full hypervapotron regime should be achieved in these operating conditions. The steady-state analysis allows the numerical evaluation of the heat transfer coefficients between Cu and water; these are then used as input for the simplified, purely thermal (solid only) analysis of the actual transient problem for the full collector. The results of the simplified model, which allows a huge reduction of the computational effort, are successfully benchmarked against those of a comprehensive thermal–hydraulic simulation. The computed peak Cu temperature is below the acceptable limit under the steady-state (time averaged

  10. Expanding the operating space of ICRF on JET with a view to ITER

    International Nuclear Information System (INIS)

    Lamalle, P.U.; Bonheure, G.; Durodie, F.; Lerche, E.; Lyssoivan, A.; Van Eester, D.; Weyssow, B.; Mantsinen, M.J.; Heikkinen, J.; Salmi, A.; Santala, M.I.K.; Noterdaeme, J.M.; Bovkov, V.V.; Alper, B.; Beaumont, P.; Blackman, T.; Vries, P. de; Gowers, C.; Felton, R.; Kiptily, V.; Lawson, K.; Lomas, P.; Mayoral, M.L.; Monakhov, I.; Popovichev, S.; Sharapov, S.; Bertalot, L.; Castaldo, C.; Tardocchi, M.; La Luna, E. de; Eriksson, L.G.; Baar, M. de; Meo, F.; Mironov, M.; Nunes, I.; Piazza, G.; Noterdaeme, J.M.

    2004-01-01

    The paper reports on ITER-relevant ICRF (ion cyclotron resonance frequency) physics investigated on JET in 2003 and early 2004: minority heating of He 3 and D in H plasmas, minority heating of tritium in D, investigations of finite Larmor radius effects on the RF-induced high-energy tails, fast wave heating and current drive, and new results on the heating efficiency of ICRF antennas. ELM (edge localized mode) studies using fast RF measurements, experimental demonstration of a new ELM-tolerant antenna matching scheme, and technical enhancements planned on the JET ICRF system for 2005, themselves likewise strongly driven by the preparation for ITER, are also summarized. (authors)

  11. Preventive maintenance program of motorized operated valves (MOV) at Cernavoda NPP

    International Nuclear Information System (INIS)

    Groza, M.; Moldoveanu, Edy

    2001-01-01

    This is a Power Point presentation. The following objectives are addressed: A. Determine the target of MOV program; B. Define the strategy for MOV; C. Establish the MOV program execution phases; D. Identification of key parameters; E. Examples. The target of MOV program is to improve the safety by ensuring the adequacy of safety valves and the reliability of safety equipment and, subsequently, to ensure the economic operation of the plant. Consequences of MV malfunction are indicated. The strategy for MOV program development is both general, namely, to define the minimal requirements of preventive /corrective maintenance activities for all MOV's according to design/ manufacture specification and particular, namely to identify MV's specific problems and the need for increasing/decreasing the preventing maintenance tasks or frequency established in 'general' MOV program. Strategy for MOV program development implies: - Establish MOV program applicability; - Develop diagnostic strategy (define key parameters ); - Perform program for engineering review; - Establish program for preventive maintenance; - Revise procedures for operating and maintenance tests; - Dynamic evaluation of MOV. The program execution phases are listed as follows: 1. Perform risk assessment of the MOV's to determine criticality level (program applicability); 2. Collect data to fill in MOV Application Data Sheet; 3. Perform engineering review to determine functional parameters acceptable range and determine key parameters; 4. Analysis for maintenance tasks / frequencies selection and determination of implementing actions (engineer review); 5. Prepare work packages for availability confirmation; 6. Schedule and plan corrective actions or provide input to other programs; 7. Schedule and plan implementing actions in preparation for program field execution; 8. Program field implementation; 9. Program monitoring, evaluation and optimization. The criteria defining the key operational and maintenance

  12. Control software architecture and operating modes of the Model M-2 maintenance system

    Energy Technology Data Exchange (ETDEWEB)

    Satterlee, P.E. Jr.; Martin, H.L.; Herndon, J.N.

    1984-04-01

    The Model M-2 maintenance system is the first completely digitally controlled servomanipulator. The M-2 system allows dexterous operations to be performed remotely using bilateral force-reflecting master/slave techniques, and its integrated operator interface takes advantage of touch-screen-driven menus to allow selection of all possible operating modes. The control system hardware for this system has been described previously. This paper describes the architecture of the overall control system. The system's various modes of operation are identified, the software implementation of each is described, system diagnostic routines are described, and highlights of the computer-augmented operator interface are discussed. 3 references, 5 figures.

  13. Control software architecture and operating modes of the Model M-2 maintenance system

    International Nuclear Information System (INIS)

    Satterlee, P.E. Jr.; Martin, H.L.; Herndon, J.N.

    1984-04-01

    The Model M-2 maintenance system is the first completely digitally controlled servomanipulator. The M-2 system allows dexterous operations to be performed remotely using bilateral force-reflecting master/slave techniques, and its integrated operator interface takes advantage of touch-screen-driven menus to allow selection of all possible operating modes. The control system hardware for this system has been described previously. This paper describes the architecture of the overall control system. The system's various modes of operation are identified, the software implementation of each is described, system diagnostic routines are described, and highlights of the computer-augmented operator interface are discussed. 3 references, 5 figures

  14. Design of a MGy radiation tolerant resolver-to-digital convertor IC for remotely operated maintenance in harsh environments

    Energy Technology Data Exchange (ETDEWEB)

    Leroux, Paul, E-mail: paul.leroux@kuleuven.be [KU Leuven, Dept. of Electrical Engineering (ESAT), AdvISe, Kleinhoefstraat 4, 2440 Geel (Belgium); Van Koeckhoven, Wesley; Verbeeck, Jens [KU Leuven, Dept. of Electrical Engineering (ESAT), AdvISe, Kleinhoefstraat 4, 2440 Geel (Belgium); Van Uffelen, Marco; Esqué, Salvador; Ranz, Roberto; Damiani, Carlo [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Hamilton, David [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France)

    2014-10-15

    During future ITER maintenance operations, sensors and their embarked electronics will be exposed to a hostile and radioactive environment. This paper presents the design of a MGy radiation tolerant 16 bit resolver-to-digital converter (RDC) in 130 nm CMOS technology. The RDC features a Type II digital tracking loop, able to track resolvers with speeds up to 300 rps, and excitation frequencies up to 4 kHz. The RDC uses two integrated ΔΣ-analog-to-digital converters (ADCs) to digitize the resolver outputs. The 16 bit, 10 kHz ADCs utilize a correlated double sampling technique to remove radiation induced offset and 1/f-noise. The front-end features a static angular resolution of 16 bits (4.2 arcsec{sub rms}) and a resolution of 10 bits (6 arcmin{sub rms}) at a rotor speed of 100 rps. The circuit has a simulated radiation tolerance exceeding 1 MGy. It has the ability to operate under temperatures up to 125 °C, and to allow multiplexing with signals from other conventional sensors for compact, robust read-out architectures.

  15. AREVA NP products and services for NPP operation and maintenance improvement

    International Nuclear Information System (INIS)

    Dechelette, Anne; Rat, Guy Le

    2009-01-01

    AREVA supplies customized services throughout the reactor improvement process according to clients' requirements: safety, performance, availability, obsolescence, operating and maintenance conditions, environment and technical assistance. Form design studies to on site modification and implementation including requalification tests, AREVA, as OEM*, has various products and services in the field of Engineering and Upgrading to satisfy client demands. In keeping with Inpo's AP913 approach, AREVA is particularly skilled in this methodology to help utilities improve availability factor and maintenance programs. AREVA has customized its services to many utilities in cooperating with local partners, suppliers, and engineering service providers through partnerships, consortiums, joint ventures, etc. AREVA's knowledge of the fleet's operation and maintenance experience helps NPP clients to identify the most cost effective improvements and approaches. Different examples of modifications of modifications and improvements performed in France and abroad illustrate AREVA's involvement in the NPP continuous upgrade process

  16. Assessment of reliability and maintenance of motor operated valves at Finnish NPPS

    International Nuclear Information System (INIS)

    Laakso, K.; Haenninen, S.; Simola, K.

    1994-01-01

    This paper summarizes two studies on motor operated valve (MOV) failure and maintenance experiences in Finnish nuclear power plants. In the first study, described in section 2 of this paper, the failure reports of MOVs at Finnish BWR units from a nine years' time period were analyzed in a systematic way. The dominant failure mechanisms were identified and time-dependencies in failure occurrence were studied. This study initiated an experience based reliability centered maintenance (RCM) analysis of motor operated valve drives, which is summarized in chapter 3 of this paper. The RCM analysis resulted in the identification and proposal of the most suitable and effective maintenance tasks for consideration. 9 refs, 3 figs, 1 tab

  17. Ageing of reinforced concrete pipes subjected to seawater in nuclear plants: optimization of maintenance operations

    International Nuclear Information System (INIS)

    Auge, L.; Capra, B.; Lasne, M.; Benefice, P.; Comby, R.

    2007-01-01

    Seaside nuclear power plants have to face the ageing of nuclear reactor cooling piping systems. In order to minimize the duration of the production unit shutdown, maintenance operations have to be planned well in advance. In a context where owners of infrastructures tend to extend the life span of their goods while having to keep the safety level maximum, it is more and more important to develop high level expertise and know-how in management of infrastructures life cycle. A patented monitoring technique based on optic fiber sensors, has been designed. This preventive maintenance enables the owner to determine criteria for network replacement based on degradation impacts. A methodology to evaluate and optimize operation budgets, depending on predictions of future functional deterioration and available maintenance solutions, has been developed and applied. (authors)

  18. Establishment of computer aided technology for operation, maintenance, and core management

    International Nuclear Information System (INIS)

    Iguchi, Masaki; Isomura, Kazutoshi; Okawa, Tsuyoshi; Sakurai, Naoto

    2003-01-01

    In Fugen, the accumulated know-how of skilled operators, maintenance engineers, and core management engineers have been systematized by using the latest computer technology. These computerized systems have enhanced the technology of operating, maintenance and core management. This report describes the development of a reactor feed water control system with fuzzy logic, a refueling support system, and an automatic refueling planning system. Since operation of reactor feedwater control at low power requires a delicate operational technique and the knowledge and experience of operators, the application of a fuzzy algorithm was deemed effective in Fugen. Its good performance comparable to that of experienced operators can be realized. The fuel-handling operation takes proposed plans, fuel management and efficient operation by skilled operators. AI technology was applied to fuel-handling support system using past operation results and experience of skilled operators. This system is as capable of fuel-handling as skilled operators. Planning an adequate fuel loading pattern is time-consuming even for expert core management engineers. The Automatic Refueling Planning System (ARPS) was developed using Genetic Algorithms (GA) and a Simulated Annealing (SA). It has been verified that long-term fuel loading patterns of the Fugen NPS evaluated by ARPS are equivalent to that of an expert core management engineer. (author)

  19. Operation and maintenance manual for the temporary septic holding tank at the 100-D remedial action support facility. Revision 2

    International Nuclear Information System (INIS)

    Kelty, G.G.

    1996-10-01

    This manual was prepared to provide detailed information for the operation and maintenance of the sanitary wastewater holding system at the 100-D Remedial Action Support Facility located in the 100-DR-1 Operable Unit at the Hanford Site. This document describes operations, including the type and frequency of required maintenance, and system failure response procedures

  20. Operation and maintenance manual for the temporary septic holding tank at the 100-D remedial action support facility. Revision 1

    International Nuclear Information System (INIS)

    Kelty, G.G.

    1996-09-01

    This manual provides detailed information for the operation and maintenance of the sanitary wastewater holding system at the 100-D Remedial Action Support Facility located in the 100-DR-1 Operable Unit of the Hanford Site. This document describes operations, including the type and frequency of required maintenance, and system failure response procedures

  1. 43 CFR 404.40 - What is the non-Federal share of operation, maintenance, and replacement costs?

    Science.gov (United States)

    2010-10-01

    ... Cost-Sharing § 404.40 What is the non-Federal share of operation, maintenance, and replacement costs? You are required to pay 100 percent of the operation, maintenance, and replacement costs of any rural... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false What is the non-Federal share of operation...

  2. The mapping and preparation of human resources for NPP’S operation and maintenance in Indonesia

    International Nuclear Information System (INIS)

    Moch-Djoko Birmano; Yohanes Dwi Anggoro

    2013-01-01

    The preparation of the competent human resources (HRs) is one of the basic infrastructure of NPP’s development. IAEA recommends that at the initial activity in preparation of human resources for NPP is doing Business Process Mapping by identifying the knowledge, skills and abilities of required human resources to carry out the operation and maintenance of NPPs. This study aims to mapping and preparing of human resources for NPP’s operation and maintenance in Indonesia. The method used are mapping business processes at operation and maintenance stage of NPP, identifying positions, conducting surveys with questionnaires and calculations, and data analysis. Surveys and questionnaires to determine the level of technical competence of personnel in BATAN at operation and maintenance stage. Analysis using the Method of Gap Analysis with human resources Competency Standards Criteria based on technical competence qualifications. This study uses the assumption that the nuclear power plant will be built 2 units (twin) and start operation in 2027. The results showed that from the aspect of education, BATAN able to meet the needs of human resources at 53.64 to 73.75%. While from the aspect of training and specific work experience, participation level of BATAN’s human resources is still very low of IAEA requirements. This case caused because young human resources in BATAN who have educational qualifications, experience, training and technical certifications in the field of operation and maintenance of nuclear power plants is still limited. Based on this, there should be preparation of NPP’s human resources with establish NPP’s human resources development program based on required qualifications. (author)

  3. Lessons learned from the Maintenance Rule implementation at Northeast Utilities operating plants

    International Nuclear Information System (INIS)

    Hastings, K.B.; Khalil, Y.F.; Johnson, W.

    1996-01-01

    The Maintenance Rule as described in 10CFR50.65 requires holders of all operating nuclear power plants to monitor the performance of structures, systems, and components (SSCs) against licensee-established performance criteria. The Industry with the assistance of the Nuclear Energy Institute (NEI) developed a guideline, which includes all parts of the Maintenance Rule, to establish these performance criteria while incorporating safety and reliability of the operating plants. The NUMARC 93-01 Guideline introduced the term ''Risk Significant'' to categorize subsets of the SSCs which would require increased focus, from a Maintenance Rule perspective, in setting their performance criteria. Northeast Utilities Company (NU) operates five nuclear plants three at Millstone Station in Waterford, Connecticut; the Connecticut Yankee plant in Haddam Neck, Connecticut; and the Seabrook Station in Seabrook, New Hampshire. NU started the implementation process of the Maintenance Rule program at its five operating plants since early 1994, and have identified a population of risk significant SSCs at each plant. Recently, Northeast Utilities' Maintenance Rule Team re-examined the initial risk significant determinations to further refine these populations, and to establish consistencies among its operating units. As a result of the re-examination process, a number of inconsistencies and areas for improvement have been identified. The lessons learned provide valuable insights to consider in the future as one implements more risk based initiatives such as Graded QA and Risk-Based ISI and IST. This paper discusses the risk significance criteria, how Northeast Utilities utilized NUMARC 93-01 Guideline to determine the risk significant SSCs for its operating plants, and lessons learned. The results provided here do not include the Seabrook Station

  4. Maintenance self-assessments - An INPO [Institute of Nuclear Power Operation] perspective

    International Nuclear Information System (INIS)

    Subalusky, W.T.

    1990-01-01

    In March 1987, all nuclear utilities in the US were requested by the Institute of Nuclear Power Operations (INPO) to perform a self-assessment of their maintenance programs. The goal of these self-assessments was to have each station identify any existing problem areas in maintenance in clear and sufficient detail to determine the root causes of the problems and to provide a foundation for subsequent corrective actions. The self-assessments were to be performed by each nuclear station using the INPO document Guidelines for the Conduct of Maintenance at Nuclear Power Stations. By December 1987, 72 of 74 stations had completed the self-assessments, and by the middle of 1988, all stations had completed this systematic review of their maintenance programs. As part of an industry plan to ensure continued improvements in maintenance, INPO is following up on the effectiveness of these self-assessments during the course of plant evaluation visits. This presentation briefly reviews the approaches to self-assessment of the station's maintenance programs, some of the lessons learned from this effort, and the results, to date, of INPO follow-up efforts in this area

  5. 75 FR 78601 - Drawbridge Operation Regulations; Hackensack River, Jersey City, NJ, Maintenance

    Science.gov (United States)

    2010-12-16

    ... Operation Regulations; Hackensack River, Jersey City, NJ, Maintenance AGENCY: Coast Guard, DHS. ACTION... 3.1, across the Hackensack River, at Jersey City, New Jersey. Under this temporary deviation a two.... SUPPLEMENTARY INFORMATION: The Witt Penn Bridge, across the Hackensack River at mile 3.1 has a vertical...

  6. 76 FR 11959 - Drawbridge Operation Regulations; Hackensack River, Jersey City, NJ, Maintenance

    Science.gov (United States)

    2011-03-04

    ... Operation Regulations; Hackensack River, Jersey City, NJ, Maintenance AGENCY: Coast Guard, DHS. ACTION... 3.1, across the Hackensack River, at Jersey City, New Jersey. The deviation is necessary to perform... River at mile 3.1 has a vertical clearance in the closed position of 35 feet at mean high water and 40...

  7. 33 CFR 208.10 - Local flood protection works; maintenance and operation of structures and facilities.

    Science.gov (United States)

    2010-07-01

    ... shall be brought to a satisfactory condition or shall be promptly replaced. Diesel and gasoline engines... machines, fuel for gasoline or diesel powered equipment, and flash lights or lanterns for emergency... the efficient operation and maintenance of all of the structures and facilities during flood periods...

  8. IVO Group wins its first operation and maintenance contract in Indonesia

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    Indonesia is one of the world's fastest growing power markets, with electricity demand rising by some 13 % annually: Finland's IVO has recently teamed up with an Indonesian partner to tap into this lucrative and competitive market. IVO's contract signed in March 1997, covers the operation and maintenance of two coal-fired power plants for a period of ten years

  9. Manpower and training requirements for operation and maintenance of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Shah, J.C.

    1975-01-01

    The experience in India with regard to the staffing of nuclear power station operations and maintenance is encouraging in the sense that given the effort and time, developing countries should not find it unduly difficult to meet their requirements. (orig.) [de

  10. Plant design and layout of the different buildings with respect to safety, operational and maintenance requirements

    International Nuclear Information System (INIS)

    Liebich, H.

    1981-01-01

    The descriptions and pictures in this lecture show that the arrangement of the buildings and the location of components and systems are based on proven ideas with the aim to fulfil safety, operational and maintenance requirements also from the point of view of plant layout. (orig.)

  11. Elements for designing ALARA programmes for the maintenance and routine operations of nuclear facilities

    International Nuclear Information System (INIS)

    Lefaure, C.; Croft, J.R.

    1991-01-01

    This article briefly reviews the three fundamental elements for designing ALARA programmes for the maintenance and routine operations of nuclear facilities. These are the need for commitment of all parties involved, the need for specific ALARA organizational structures and the systematic use of ALARA tools. (UK)

  12. Impact of improved operation and maintenance on cohesive sediment transport in Gezira Scheme, Sudan

    NARCIS (Netherlands)

    Osman, I.S.E.

    2015-01-01

    Summary

    Efficient operation and maintenance of irrigation schemes are needed for improving the hydraulic performance of the canals, enhancing the crop yields and insuring sustainable production. There is a great need to enhance the researches and for a variety of tools such as

  13. Costs of construction, operation and maintenance of nuclear power plants - determinant factors

    International Nuclear Information System (INIS)

    Silva, R.A. da

    1981-01-01

    A study about the construction costs of the Angra-1 nuclear power plant, including direct costs, equipment costs, installation and indirect costs such as: engineering, job-training and administration is presented. The operation and maintenance costs of the Angra-1 nuclear power plant and costs of energy generation are still studied. (E.G.) [pt

  14. Community College Finance: A Cost Analysis of Community College Expenditures Related to Maintenance and Operations

    Science.gov (United States)

    Collins, Michael T.

    2011-01-01

    The purpose of this study is to develop a costing model for maintenance and operations expenditures among 16 single-campus California community college districts and assess the impact of a variety of variables including size of student enrollment, physical plant age, acreage, gross square footage, and general obligation facility bonds on district…

  15. Traditional Learning vs Virtual Learning in maintenance operations thoughts and reflections from a safety perspective

    NARCIS (Netherlands)

    Martinetti, Alberto; 't Hart, Koen; Bernatik, Ales; Kocurkova, Lucie; Jorgensen, Kirsten

    2018-01-01

    Flexibility in maintenance operations is one of the requirements for a successful management of capital asset industries nowadays. It demands both the deployment of technology, equipment and man-forces and to provide effective training to the technicians for maintaining the assets in a correct and

  16. Pilgrim Nuclear Power Station, Unit 1. Fifth semiannual operating and maintenance report, July--December 1974

    International Nuclear Information System (INIS)

    1974-01-01

    During this period the reactor was critical for 3,550.3 hrs and the net electrical power generated was 1,973,033 MWH. Information is presented concerning operations, maintenance, radioactive effluents, environmental monitoring, and radioactive materials released to unrestricted areas. (U.S.)

  17. Reliability analysis and risk-based methods for planning of operation & maintenance of offshore wind turbines

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard

    2017-01-01

    for extreme and fatigue limit states are presented. Operation & Maintenance planning often follows corrective and preventive strategies based on information from condition monitoring and structural health monitoring systems. A reliability- and risk-based approach is presented where a life-cycle approach...

  18. Operation, Maintenance and Management of Wastewater Treatment Facilities: A Bibliography of Technical Documents.

    Science.gov (United States)

    Himes, Dottie

    This is an annotated bibliography of wastewater treatment manuals. Fourteen manuals are abstracted including: (1) A Planned Maintenance Management System for Municipal Wastewater Treatment Plants; (2) Anaerobic Sludge Digestion, Operations Manual; (3) Emergency Planning for Municipal Wastewater Treatment Facilities; (4) Estimating Laboratory Needs…

  19. EVALUATION OF THE IMPLEMENTATION OF OPERATIONS AND MAINTENANCE PROGRAMS IN NEW JERSEY SCHOOLS

    Science.gov (United States)

    The Asbestos Hazard Emergency Response Act (AHERA) required all schools to develop and implement an asbestos management plan (AMP). The key component of the AMP is the operations and maintenance (O&M) program. A study was conducted to evaluate the implementation of O&M programs a...

  20. ITER TASK T252 (1995):Gamma radiation testing of a GaAs operational amplifier for instrument applications

    International Nuclear Information System (INIS)

    Hiemstra, D.

    1996-03-01

    The purpose of this 1995 ITER task was : to build an improved operational amplifier using GaAs MESFET technology, to build a reference voltage subcircuit using GaAs MESFET technology and to investigate the potential of GaAs HBT's to improve the noise performance of the GaAs MESFET operational amplifier. This work addresses the need for instrumentation-grade components to read sensors in an experimental fusion reactor, where the anticipated total dose for a useful service life is 3Grad(GaAs). It is an extension of our 1994 work. 3 tabs., 6 figs

  1. Main indicators used in french PWR units for safety, operation and maintenance

    International Nuclear Information System (INIS)

    Guio, J.M. de

    1990-01-01

    The development of analyses aimed at improving nuclear plant operations through an optimum use of experience feedback naturally leads to the implementation of trend indicators in the fields of safety, operation and maintenance. This process, part of the more general framework of promoting safety culture, facilitates collective thinking on these matters at the local site level, and, at the national level, allows a clearer definition of the main lines of strategy and helps coordinate the resulting actions

  2. Operation and maintenance of the RB reactor, Annual report for 1977

    International Nuclear Information System (INIS)

    Sotic, O.; Vranic, S.

    1977-01-01

    The annual report for 1977 includes the following: utilization of the RB reactor; new regulations and instructions for reactor operation; improvement of experimental possibilities of the RB reactor; state of the reactor equipment; dosimetry and radiation protection; reactor staff. Five annexes are concerned with: testing the properties of preamplifiers for linear and logarithmic experimental channels; properties of the neutron converter; maintenance of the reactor equipment; purchase of new equipment; and the program for training reactor operators

  3. Operation and maintenance experience at the General Atomic Company's TRIGA reactor facility at San Diego, California

    International Nuclear Information System (INIS)

    Whittemore, W.L.; Stout, W.A.; Shoptaugh, J.R.; Chesworth, R.H.

    1982-01-01

    Since the startup of the original 250 kW TRIGA Mark I reactor in 1958, General Atomic Company has accumulated nearly 24 years of operation and maintenance experience with this type of reactor. In addition to the nearly 24 years of experience gained on the Mark I, GA has operated the 1.5 MW Advanced Prototype Test Reactor (Mark F) for 22 years and operated a 2 MW below-ground TRIGA Mark III for five years. Information obtained from normal and abnormal operation are presented. (author)

  4. On risk-based operation and maintenance of offshore wind turbine components

    DEFF Research Database (Denmark)

    Nielsen, Jannie Jessen; Sørensen, John Dalsgaard

    2011-01-01

    Operation and maintenance are significant contributors to the cost of energy for offshore wind turbines. Optimal planning could rationally be based on Bayesian pre-posterior decision theory, and all costs through the lifetime of the structures should be included. This paper contains a study...... of a generic case where the costs are evaluated for a single wind turbine with a single component. Costs due to inspections, repairs, and lost production are included in the model. The costs are compared for two distinct maintenance strategies, namely with and without inclusion of periodic imperfect...

  5. Risk assessment of maintenance operations: the analysis of performing task and accident mechanism.

    Science.gov (United States)

    Carrillo-Castrillo, Jesús A; Rubio-Romero, Juan Carlos; Guadix, Jose; Onieva, Luis

    2015-01-01

    Maintenance operations cover a great number of occupations. Most small and medium-sized enterprises lack the appropriate information to conduct risk assessments of maintenance operations. The objective of this research is to provide a method based on the concepts of task and accident mechanisms for an initial risk assessment by taking into consideration the prevalence and severity of the maintenance accidents reported. Data were gathered from 11,190 reported accidents in maintenance operations in the manufacturing sector of Andalusia from 2003 to 2012. By using a semi-quantitative methodology, likelihood and severity were evaluated based on the actual distribution of accident mechanisms in each of the tasks. Accident mechanisms and tasks were identified by using those variables included in the European Statistics of Accidents at Work methodology. As main results, the estimated risk of the most frequent accident mechanisms identified for each of the analysed tasks is low and the only accident mechanisms with medium risk are accidents when lifting or pushing with physical stress on the musculoskeletal system in tasks involving carrying, and impacts against objects after slipping or stumbling for tasks involving movements. The prioritisation of public preventive actions for the accident mechanisms with a higher estimated risk is highly recommended.

  6. Iterative approximation of the solution of a monotone operator equation in certain Banach spaces

    International Nuclear Information System (INIS)

    Chidume, C.E.

    1988-01-01

    Let X=L p (or l p ), p ≥ 2. The solution of the equation Ax=f, f is an element of X is approximated in X by an iteration process in each of the following two cases: (i) A is a bounded linear mapping of X into itself which is also bounded below; and, (ii) A is a nonlinear Lipschitz mapping of X into itself and satisfies ≥ m |x-y| 2 , for some constant m > 0 and for all x, y in X, where j is the single-valued normalized duality mapping of X into X* (the dual space of X). A related result deals with the iterative approximation of the fixed point of a Lipschitz strictly pseudocontractive mapping in X. (author). 12 refs

  7. Design, manufacture and initial operation of the beryllium components of the JET ITER-like wall

    Energy Technology Data Exchange (ETDEWEB)

    Riccardo, V., E-mail: valeria.riccardo@ccfe.ac.uk [EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Lomas, P.; Matthews, G.F. [EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Nunes, I. [Associação EURATOM-IST, IPFN – Laboratório Associado, IST, Lisbon (Portugal); JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Thompson, V. [EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Villedieu, E. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom)

    2013-10-15

    Highlights: ► 40 m{sup 2} of plasma facing surface covered with bulk Be re-using existing supports, designed for C-based tiles (hence for much lower disruption loads). ► Optimization of power handling to allow compatibility with higher (×1.5) and longer (×2) neutral beam power. ► Beryllium re-cycling. ► Machining and cleaning to ultra high vacuum standards of <350 μm thin castellations in Be. ► Quality control to minimize installation problems (proto-types, full scale jigs, inspections). -- Abstract: The aim of the JET ITER-like wall project was to provide JET with the plasma facing material combination now selected for the DT phase of ITER (bulk beryllium main chamber limiters and a full tungsten divertor) and, in conjunction with the upgraded neutral beam heating system, to achieve ITER relevant conditions. The design of the bulk Be plasma facing components had to be compatible with increased heating power and pulse length, as well as to reuse the existing tile supports originally designed to cope with disruption loads from carbon based tiles and be installed by remote handling. Risk reduction measures (prototypes, jigs, etc.) were implemented to maximize efficiency during the shutdown. However, a large number of clashes with existing components not fully captured by the configuration model occurred. Restarting the plasma on the ITER-like Wall proved much easier than for the carbon wall and no deconditioning by disruptions was observed. Disruptions have been more threatening than expected due to the reduced radiative losses compared to carbon, leaving most of the plasma magnetic energy to be conducted to the wall and requiring routine disruption mitigation. The main chamber power handling has achieved and possibly exceeded the design targets.

  8. Design, manufacture and initial operation of the beryllium components of the JET ITER-like wall

    International Nuclear Information System (INIS)

    Riccardo, V.; Lomas, P.; Matthews, G.F.; Nunes, I.; Thompson, V.; Villedieu, E.

    2013-01-01

    Highlights: ► 40 m 2 of plasma facing surface covered with bulk Be re-using existing supports, designed for C-based tiles (hence for much lower disruption loads). ► Optimization of power handling to allow compatibility with higher (×1.5) and longer (×2) neutral beam power. ► Beryllium re-cycling. ► Machining and cleaning to ultra high vacuum standards of <350 μm thin castellations in Be. ► Quality control to minimize installation problems (proto-types, full scale jigs, inspections). -- Abstract: The aim of the JET ITER-like wall project was to provide JET with the plasma facing material combination now selected for the DT phase of ITER (bulk beryllium main chamber limiters and a full tungsten divertor) and, in conjunction with the upgraded neutral beam heating system, to achieve ITER relevant conditions. The design of the bulk Be plasma facing components had to be compatible with increased heating power and pulse length, as well as to reuse the existing tile supports originally designed to cope with disruption loads from carbon based tiles and be installed by remote handling. Risk reduction measures (prototypes, jigs, etc.) were implemented to maximize efficiency during the shutdown. However, a large number of clashes with existing components not fully captured by the configuration model occurred. Restarting the plasma on the ITER-like Wall proved much easier than for the carbon wall and no deconditioning by disruptions was observed. Disruptions have been more threatening than expected due to the reduced radiative losses compared to carbon, leaving most of the plasma magnetic energy to be conducted to the wall and requiring routine disruption mitigation. The main chamber power handling has achieved and possibly exceeded the design targets

  9. Ion cyclotron resonance frequency heating in JET during initial operations with the ITER-like wall

    Czech Academy of Sciences Publication Activity Database

    Jacquet, P.; Bobkov, V.; Colas, L.; Czarnecka, A.; Lerche, E.; Mayoral, M.-L.; Monakhov, I.; Van-Eester, D.; Arnoux, G.; Brezinsek, S.; Brix, M.; Campergue, A.-L.; Devaux, S.; Drewelow, P.; Graham, M.; Klepper, C.C.; Meigs, A.; Milanesio, D.; Mlynář, Jan; Pütterich, T.; Sirinelli, A.

    2014-01-01

    Roč. 21, č. 6 (2014), 061510-061510 ISSN 1070-664X. [Topical conference on radio frequency power in plasmas/20./. Sorrento, 25.06.2013-28.06.2013] Institutional support: RVO:61389021 Keywords : JET * ITER-like wall * ICRF heating * impurities * sawtooth * simulation * transport Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 2.142, year: 2014 http://scitation.aip.org/content/aip/journal/pop/21/6/10.1063/1.4884354

  10. Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)

    Energy Technology Data Exchange (ETDEWEB)

    Shimizu, Atsushi, E-mail: shimizu.atsushi35@jaea.go.jp [HTTR Operation Section, Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393 (Japan); Kawamoto, Taiki [HTTR Operation Section, Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393 (Japan); Tochio, Daisuke [HTTR Reactor Engineering Section, Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393 (Japan); Saito, Kenji; Sawahata, Hiroaki; Honma, Fumitaka; Furusawa, Takayuki; Saikusa, Akio [HTTR Operation Section, Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393 (Japan); Takada, Shoji [HTTR Reactor Engineering Section, Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393 (Japan); Shinozaki, Masayuki [HTTR Operation Section, Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393 (Japan)

    2014-05-01

    To establish the technical basis of HTGR (High Temperature Gas cooled Reactor), the long term high temperature operation using HTTR was carried out in the high temperature test operation mode during 50-day since January till March, 2010. It is necessary to establish the technical basis of operation and maintenance by demonstrating the stability of plant during long-term operation and the reliability of components and facilities special to HTGRs, in order to attain the stable supply of the high temperature heat to the planned heat utilization system of HTTR. Test data obtained in the operation were evaluated for the technical issues which were extracted before the operation. As the results, it was confirmed that the temperatures and flow rate of primary and secondary coolant were well controlled within sufficiently small deviation against the disturbance by the atmospheric temperature variation in daily. Stability and reliability of the components and facility special to HTGRs was demonstrated through the long term high temperature operation by evaluating the heat transfer performance of high temperature components, the stability performance of pressure control to compensate helium gas leak, the reliability of the dynamic components such as helium gas circulators, the performance of heat-up protection of radiation shielding. Through the long term high temperature operation of HTTR, the technical basis for the operation and maintenance technology of HTGRs was established.

  11. Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)

    International Nuclear Information System (INIS)

    Shimizu, Atsushi; Kawamoto, Taiki; Tochio, Daisuke; Saito, Kenji; Sawahata, Hiroaki; Honma, Fumitaka; Furusawa, Takayuki; Saikusa, Akio; Takada, Shoji; Shinozaki, Masayuki

    2014-01-01

    To establish the technical basis of HTGR (High Temperature Gas cooled Reactor), the long term high temperature operation using HTTR was carried out in the high temperature test operation mode during 50-day since January till March, 2010. It is necessary to establish the technical basis of operation and maintenance by demonstrating the stability of plant during long-term operation and the reliability of components and facilities special to HTGRs, in order to attain the stable supply of the high temperature heat to the planned heat utilization system of HTTR. Test data obtained in the operation were evaluated for the technical issues which were extracted before the operation. As the results, it was confirmed that the temperatures and flow rate of primary and secondary coolant were well controlled within sufficiently small deviation against the disturbance by the atmospheric temperature variation in daily. Stability and reliability of the components and facility special to HTGRs was demonstrated through the long term high temperature operation by evaluating the heat transfer performance of high temperature components, the stability performance of pressure control to compensate helium gas leak, the reliability of the dynamic components such as helium gas circulators, the performance of heat-up protection of radiation shielding. Through the long term high temperature operation of HTTR, the technical basis for the operation and maintenance technology of HTGRs was established

  12. MOVES: A knowledge-based system for maintenance planning for motor-operated valves

    International Nuclear Information System (INIS)

    Winter, M.

    1987-01-01

    Over the past several years, knowledge-based expert systems have emerged as an important part of the general research area known as artificial intelligence. This paper describes a cooperative effort between faculty members at Iowa State University and engineers at the Duane Arnold Energy Center [a 545-MW(electric) boiling water reactor operated by Iowa Electric Light and Power Company] to explore the development of an advisory system for valve maintenance planning. This knowledge-based program, known as Motor-Operated Valves Expert System (MOVES), has a data base that currently includes safety-related motor-operated valves (∼117 valves). Valve maintenance was selected as the subject for the expert system because of the importance of valves in nuclear plant and their impact of plant availability. MOVES is being developed using the microcomputer-(IBM compatible) based expert system tool INSIGHT2+. The authors have found that the project benefits both the university and the utility

  13. Risk-Based Operation and Maintenance Planning for Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Nielsen, Jannie Jessen; Sørensen, John Dalsgaard

    2010-01-01

    Operation and maintenance (O&M) are large contributors to the cost of energy for offshore wind turbines. Optimal planning of O&M should include use of inspections and monitoring results to make decisions that minimize the expected costs through the lifetime of the structures. For offshore...... structures it is especially important because of the dependence on weather windows for inspections and repairs to be possible. A model has been developed to estimate the expected costs to corrective and condition based maintenance for a wind turbine with a single component. The deterioration of the component...... is simulated, and the expected costs are found for different strategies. An application example shows that condition based maintenance has the potential of reducing the costs, and a risk based approach can be used to find the optimal strategy for O&M. Further the influence of failure rate and damage parameters...

  14. Wind turbine blade life-time assessment model for preventive planning of operation and maintenance

    DEFF Research Database (Denmark)

    Florian, Mihai; Sørensen, John Dalsgaard

    2014-01-01

    Out of the total wind turbine failure events, blade damage accounts for a substantial part, with some studies estimating it at around 23%. Current operation and maintenance (O&M) practices typically make use of corrective type maintenance as the basic approach, implying high costs for repair...... of information on the blades structural health to the decision maker. Further, inspections of the blades are often performed in connection with service. In light of the obtained information, a preventive type of maintenance becomes feasible, with the potential of predicting the blades remaining life to support O......&M decisions for avoiding major failure events. The present paper presents a fracture mechanics based model for estimating the remaining life of a wind turbine blade, focusing on the crack propagation in the blades adhesive joints. A generic crack propagation model is built in Matlab based on a Paris law...

  15. Wind Turbine Blade Life-Time Assessment Model for Preventive Planning of Operation and Maintenance

    DEFF Research Database (Denmark)

    Florian, Mihai; Sørensen, John Dalsgaard

    2015-01-01

    Out of the total wind turbine failure events, blade damage accounts for a substantial part, with some studies estimating it at around 23%. Current operation and maintenance (O&M) practices typically make use of corrective type maintenance as the basic approach, implying high costs for repair...... of information on the blades structural health to the decision maker. Further, inspections of the blades are often performed in connection with service. In light of the obtained information, a preventive type of maintenance becomes feasible, with the potential of predicting the blades remaining life to support O......&M decisions for avoiding major failure events. The present paper presents a fracture mechanics based model for estimating the remaining life of a wind turbine blade, focusing on the crack propagation in the blades adhesive joints. A generic crack propagation model is built in Matlab based on a Paris law...

  16. Design of the system of maintenance operations occupational safety and health database application of nuclear power station

    International Nuclear Information System (INIS)

    Wang Xuehong; Li Xiangyang; Ye Yongjun

    2011-01-01

    Based on the KKS code of building equipment in nuclear power station, this paper introduces the method of establishing the system of maintenance operation occupational safety and health database application. Through the application system of maintenance occupational safety and health database, it can summarize systematically all kinds of maintenance operation dangerous factor of nuclear power station, and make a convenience for staff to learn the maintenance operation dangerous factors and the prevention measures, so that it can achieve the management concept of 'precaution crucial, continuous improvement' that advocated by OSHMS. (authors)

  17. Development of preventive maintenance technology and advanced service equipment for operating nuclear power plants

    International Nuclear Information System (INIS)

    Abe, Kazuhiro; Sumikawa, Masaharu; Hirakawa, Hiromasa; Arakawa, Tadao; Hasegawa, Kunio; Kato, Kanji.

    1990-01-01

    Hitachi Ltd. as a manufacturer of nuclear power plants has carried out the consistent general preventive maintenance activities from the planning of the plants and the design of maintainability in the construction phase to the planning and working of preventive maintenance in the operation and maintenance phase, and exerted efforts to heighten the capacity ratio and reliability of the plants. For the purpose, the steady activities of reliability improvement have been carried out throughout the whole company, and the rationalization of the planning and management of the preventive maintenance with a computer and the development of the robots to which Al is applied have been promoted. As the technology of upgrading the facilities, boron racks, the control rods having long life and so on were developed, and their practical use is advanced. Moreover for the future, the development of the diagnostic technology on material deterioration using superconductive quantum interference devices (SQUID) is in progress. The preventive maintenance activities in Hitachi Ltd., the technical development for the purpose and the upgrading of the plant facilities are reported. (K.I.)

  18. Wind Turbine Blade Life-Time Assessment Model for Preventive Planning of Operation and Maintenance

    Directory of Open Access Journals (Sweden)

    Mihai Florian

    2015-09-01

    Full Text Available Out of the total wind turbine failure events, blade damage accounts for a substantial part, with some studies estimating it at around 23%. Current operation and maintenance (O&M practices typically make use of corrective type maintenance as the basic approach, implying high costs for repair and replacement activities as well as large revenue losses, mainly in the case of offshore wind farms. The recent development and evolution of condition monitoring techniques, as well as the fact that an increasing number of installed turbines are equipped with online monitoring systems, offers a large amount of information on the blades structural health to the decision maker. Further, inspections of the blades are often performed in connection with service. In light of the obtained information, a preventive type of maintenance becomes feasible, with the potential of predicting the blades remaining life to support O&M decisions for avoiding major failure events. The present paper presents a fracture mechanics based model for estimating the remaining life of a wind turbine blade, focusing on the crack propagation in the blades adhesive joints. A generic crack propagation model is built in Matlab based on a Paris law approach. The model is used within a risk-based maintenance decision framework to optimize maintenance planning for the blades lifetime.

  19. Feedback of operation and maintenance experience into evolutionary plant design (HWRs)

    International Nuclear Information System (INIS)

    Hedges, K.R.; Sanatkumar, A.; Kwon, Oh-Cheol

    1999-01-01

    The process of feeding back operation and maintenance information into the CANDU plant design process has been in constant evolution since the beginning of the CANDU program. The commissioning and operation experience from the first commercial reactors at Pickering A and Bruce A was used extensively in the design of the first generation CANDU 6 Plants. These units have been in operation for 15 years, producing electricity at an average lifetime capacity factor of about 85%. In further advancing the CANDU 6 and 9 design, greater emphasis is placed on enhancements that can reduce operational costs and further improve plant performance by reducing the planned outage time. The plant design has been improved to facilitate maintenance scheduling, equipment isolation, maintenance and post maintenance testing. Individual tasks have been analyzed as well as the interaction between tasks during outages to reduce the down time required and simplify the execution of the work. This results in shorter outages, reduced radioactive dose and reduced costs. The Utilities have continued to play an important role in CANDU 6 Evolution. Specifically; the Korea Utility KEPCO has one of the original four CANDU 6 Plants and three of the most modem. Their feedback to the designers has been very helpful. One of the most important feedback processes is through the CANDU Owners Group, which provides information exchange between members. In India eight PHWRs of 220 MWe capacity are in operation. Four reactors, also of 220 MWe capacity are in advanced stages of construction. Site construction work of two units of 500 MWe PHWRs at Tarapur will be taken up shortly. Over the years, during construction and operation of these power stations, a large amount of experience has been accumulated. Operation and maintenance experience is shared with operating stations by intensive participation of design engineers in Station Operation Review meetings, trouble shooting and root cause analysis of problems

  20. Towards a Risk-based Decision Support for Offshore Wind Turbine Installation and Operation & Maintenance

    DEFF Research Database (Denmark)

    Gintautas, Tomas; Sørensen, John Dalsgaard; Vatne, Sigrid Ringdalen

    2016-01-01

    Costs of operation & maintenance, assembly, transport and installation of offshore wind turbines contribute significantly to the total cost of offshore wind farm. These operations are mostly carried out by specific ships that have to be hired for the operational phase and for duration of installa......Costs of operation & maintenance, assembly, transport and installation of offshore wind turbines contribute significantly to the total cost of offshore wind farm. These operations are mostly carried out by specific ships that have to be hired for the operational phase and for duration...... of installation process, respectively. Duration, and therefore ship hiring costs is, among others, driven by waiting time for weather windows for weather-sensitive operations. Today, state of the art decision making criteria for weather-sensitive operations are restrictions to the significant wave height...... and the average wind velocity at reference height. However, actual limitations are physical, related to response of equipment used e.g. crane wire tension, rotor assembly motions while lifting, etc. Transition from weather condition limits to limits on physical equipment response in decision making would improve...

  1. Guide for the monitoring of radiation protection during national modification and maintenance operations. Report nr 307

    International Nuclear Information System (INIS)

    Bataille, C.; Michelet, M.; Schieber, C.

    2010-02-01

    This methodological guide aims at helping the different involved actors in designing and implementing the monitoring of radiation protection during modification and maintenance operations performed at the national level. It describes actions to be performed by each actor in order to comply with the objectives of the four steps related to the radiation protection monitoring of an operation: the design of the radiation protection monitoring during the study phase, the adaptation of this monitoring to the concerned CNPE (electricity production nuclear centre), the radiation protection monitoring during the operation performance, and the analysis of the return on experience

  2. Heat pumps: planning, optimisation, operation and maintenance; Waermepumpen. Planung - Optimierung - Betrieb - Wartung

    Energy Technology Data Exchange (ETDEWEB)

    Kunz, P. [Kunz-Beratungen, Dietlikon (Switzerland); Afjei, T. [Fachhochschule Nordwestschweiz, Institut fuer Energie am Bau, Muttenz (Switzerland); Betschart, W.; Prochaska, V. [Hochschule Luzern, Technik und Architektur, Horw (Switzerland); Hubacher, P. [Hubacher Engineering, Engelburg (Switzerland); Loehrer, R. [Scheco AG, Winterthur (Switzerland); Mueller, A. [Mueller und Pletscher AG, Winterthur (Switzerland)

    2008-01-15

    This handbook issued by the Swiss Federal Office of Energy (SFOE) in co-operation with a trade publication takes a look at the planning, optimisation, operation and maintenance of heat pumps. First of all, the basics of heat pump technology, heat pump components and refrigerants are discussed. Then, heat sources and heat distribution are looked at, followed by chapters on the integration of heat pumps into heating systems and noise protection topics. The definition of projects, commissioning and operation of heat pump systems are then discussed. Examples of installations round off the handbook.

  3. Installation, maintenance and operating manual for the Lucas-type fuel injection system of the 3 B rotary engine

    Science.gov (United States)

    1985-01-01

    The installation procedure, maintenance, adjustment and operation of a Lucas type fuel injection system for 13B rotary racing engine is outlined. Components of the fuel injection system and installation procedure and notes are described. Maintenance, adjustment, and operation are discussed.

  4. Reliability-Based Planning of Inspection, Operation and Maintenance for Offshore Oil & Gas Structures and Wind Turbines

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard

    2011-01-01

    Reliability-based cost-optimal planning of inspection, maintenance and operation has many applications. In this paper applications for planning of inspections for oil & gas jacket structures and of operation and maintenance of offshore wind turbines are described and illustrated by examples....

  5. The Development and Application of a Value-Driven Aircraft Maintenance Operations Performance Assessment Model combined with Real Options Analysis

    NARCIS (Netherlands)

    Goossens, H.G.; Beelaerts van Blokland, W.W.A.; Curran, R.

    2011-01-01

    This research paper presents the results from the development of an Aircraft Maintenance Operations Performance Assessment Model (AMOPAM). The AMOPAM is able to assess the differences in performance in between two different states or scenarios of aircraft maintenance operations and is able to

  6. 41 CFR 102-85.175 - Are the standard level services for cleaning, mechanical operation, and maintenance identified in...

    Science.gov (United States)

    2010-07-01

    ... services for cleaning, mechanical operation, and maintenance identified in an OA? 102-85.175 Section 102-85... of Service § 102-85.175 Are the standard level services for cleaning, mechanical operation, and maintenance identified in an OA? Unless specified otherwise in the OA, standard level services for cleaning...

  7. A test case of computer aided motion planning for nuclear maintenance operation

    Energy Technology Data Exchange (ETDEWEB)

    Schmitzberger, E.; Bouchet, J.L. [Electricite de France (EDF), Dept. Surveillance Diagnostic Maintenance, 78 - Chatou (France); Schmitzberger, E. [Institut National Polytechnique, CRAN, 54 - Vandoeuvre les Nancy (France)

    2001-07-01

    Needs for improved tools for nuclear power plant maintenance preparation are expressed by EDF engineering. These are an easier and better management of logistics constraints such as free spaces for motions or handling tasks. The lack of generic or well suited tools and the specificity of nuclear maintenance operation have led EDF R and D to develop its own motion planning tools in collaboration with LAAS-CNRS, Utrecht University and the software publisher CADCENTRE within the framework of the three years Esprit LTR project MOLOG. EDF users needs will be summed up in the first part of the paper under the title ''Motion feasibility studies for maintenance operation'' and then compared to the current industrial offer in the ''Software's background'''s part. The definition and objectives ''Towards motion planning tools'' follows. It explains why maintenance preparation pertains to automatic motion planning and how it makes studies much simpler. The ''MOLOG's Benchmark and first result'''s part describes the test-case used to evaluate the MOLOG project and gives an outlook at the results obtained so far. (author)

  8. A test case of computer aided motion planning for nuclear maintenance operation

    International Nuclear Information System (INIS)

    Schmitzberger, E.; Bouchet, J.L.; Schmitzberger, E.

    2001-01-01

    Needs for improved tools for nuclear power plant maintenance preparation are expressed by EDF engineering. These are an easier and better management of logistics constraints such as free spaces for motions or handling tasks. The lack of generic or well suited tools and the specificity of nuclear maintenance operation have led EDF R and D to develop its own motion planning tools in collaboration with LAAS-CNRS, Utrecht University and the software publisher CADCENTRE within the framework of the three years Esprit LTR project MOLOG. EDF users needs will be summed up in the first part of the paper under the title ''Motion feasibility studies for maintenance operation'' and then compared to the current industrial offer in the ''Software's background'''s part. The definition and objectives ''Towards motion planning tools'' follows. It explains why maintenance preparation pertains to automatic motion planning and how it makes studies much simpler. The ''MOLOG's Benchmark and first result'''s part describes the test-case used to evaluate the MOLOG project and gives an outlook at the results obtained so far. (author)

  9. ITER radio frequency systems

    International Nuclear Information System (INIS)

    Bosia, G.

    1998-01-01

    Neutral Beam Injection and RF heating are two of the methods for heating and current drive in ITER. The three ITER RF systems, which have been developed during the EDA, offer several complementary services and are able to fulfil ITER operational requirements

  10. Organization and mechanization of maintenance operations at NPPs with the WWER type reactors

    International Nuclear Information System (INIS)

    Titov, A.A.

    1983-01-01

    The structure of capital investments defining organization and mechanization of maintepance operations at NPPs with the WWER type reactors is analyzed. The trends in development of optimum decisions for organization and mechanization of repair obs at NPPs being designed taking into account the prospects of nuclear powep enginerning development, the system of NPP maintenance servicing, as well as the structure of repair-productive capacities are discussed. On the basis of the analysis of the data obtained in designing the Zaporozhskaya NPP it is shown that the capital investments for organizing and mechanization of maintenance operations at the unified NPP site with four WWER-1000 reactors reach nearly 18 roubles/kW. A conclusion is drawn that at present the design of an NPP with the WWER-1000 reactor totally meets the requirements of realization of periodic maintenance operations. It is advisable to cooperate the NPP management with that of a thermal power station from the viewpoint of using manpower, which would improve the operating conditions and labour productivity of workers engaged in repair and, consequently, reduce the capital investments and repair expenditures

  11. Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure

    Energy Technology Data Exchange (ETDEWEB)

    Di Maio, P.A. [Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo Viale delle Scienze, 90128 Palermo (Italy); Dell’Orco, G.; Furmanek, A. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Garitta, S. [Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo Viale delle Scienze, 90128 Palermo (Italy); Merola, M.; Mitteau, R.; Raffray, R. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Spagnuolo, G.A. [Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo Viale delle Scienze, 90128 Palermo (Italy); Vallone, E., E-mail: eug.vallone@gmail.com [Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo Viale delle Scienze, 90128 Palermo (Italy)

    2015-10-15

    Highlights: • ITER blanket cooling system hydraulic behaviour is studied under draining transient. • A computational approach based on the finite volume method has been followed. • Draining efficiency has been assessed in term of transient duration and residual water. • Transient duration ranges from ∼40 to 50 s, under the reference draining scenario. • Residual water is predicted to range from few tens of gram up to few kilograms. - Abstract: Within the framework of the research and development activities supported by the ITER Organization on the blanket system issues, an intense analysis campaign has been performed at the University of Palermo with the aim to investigate the thermal-hydraulic behaviour of the cooling system of a standard 20° sector of ITER blanket during the draining transient operational procedure. The analysis has been carried out following a theoretical-computational approach based on the finite volume method and adopting the RELAP5 system code. In a first phase, attention has been focused on the development and validation of the finite volume models of the cooling circuits of the most demanding modules belonging to the standard blanket sector. In later phase, attention has been put to the numerical simulation of the thermal-hydraulic transient behaviour of each cooling circuit during the draining operational procedure. The draining procedure efficiency has been assessed in terms of both transient duration and residual amount of coolant inside the circuit, observing that the former ranges typically between 40 and 120 s and the latter reaches at most ∼8 kg, in the case of the cooling circuit of twinned modules #6–7. Potential variations to operational parameters and/or to circuit lay-out have been proposed and investigated to optimize the circuit draining performances. In this paper, the set-up of the finite volume models is briefly described and the key results are summarized and critically discussed.

  12. Organizational Culture Influence On Total Productive Maintenance (TPM and Operational Performance Using RASCH Model Analysis

    Directory of Open Access Journals (Sweden)

    Mohd Norhasni Mohd Asaad

    2014-02-01

    Full Text Available Abstract. Market globalization, competitive product and services, high economic crises are the most critical factors that influence the success of the manufacturing companies in global market. Therefore it is critical to the manufacturing companies to be efficient in production and lean tool may used to achieve that.  The most frequently used is the Total Preventive Maintenance (TPM, even though there are many studies have been conducted in relation to the TPM but there is limited research in investigating the effects of the TPM on operational performance. However, the result of the studies was not consistent, where TPM practice may have positive and negative impact on operational performance. Among the reason is the culture of the organization that influenced the implementation of TPM and operational performance. Due to that this study attempts to investigate the influence of organizational culture on the TPM implementation and operational performance.  Rasch model is used in this study due to its ability in interpreting and analyzing the ability of respondents in performing the difficult items. The online questionnaires were distributed to 63 randomly selected automotive companies located at Northern Region of Malaysia.  Results of the study revealed that the organizational culture has influenced on the successful implementation of TPM and operational performance. Therefore by the implementation of TPM in outstanding organizational culture can improve operational performance.   Keyword: Total Preventive Maintenance (TPM, Lean manufacturing, Operational performance, Organizational culture, Rasch modeldoi:10.12695/ajtm.2013.6.2.2How to cite this article:Mohd Asaad, M.N and Yusoff, R.Z. (2013. Organizational Culture Influence On Total Productive Maintenance (TPM and Operational Performance Using RASCH Model Analysis . The Asian Journal of Technology Management 6 (2: 72-81. Print ISSN: 1978-6956; Online ISSN: 2089-791X.  doi:10.12695/ajtm

  13. Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

    International Nuclear Information System (INIS)

    DALE, R.N.

    2000-01-01

    A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O and M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085

  14. Operational control and maintenance integrity of typical and atypical coil tube steam generating systems

    Energy Technology Data Exchange (ETDEWEB)

    Beardwood, E.S.

    1999-07-01

    Coil tube steam generators are low water volume to boiler horsepower (bhp) rating, rapid steaming units which occupy substantially less space per boiler horsepower than equivalent conventional tire tube and water tube boilers. These units can be retrofitted into existing steam systems with relative ease and are more efficient than the generators they replace. During the early 1970's they became a popular choice for steam generation in commercial, institutional and light to medium industrial applications. Although these boiler designs do not require skilled or certified operators, an appreciation for a number of the operational conditions that result in lower unscheduled maintenance, increased reliability and availability cycles would be beneficial to facility owners, managers, and operators. Conditions which afford lower operating and maintenance costs will be discussed from a practical point of view. An overview of boiler design and operation is also included. Pitfalls are provided for operational and idle conditions. Water treatment application, as well as steam system operations not conducive to maintaining long term system integrity; with resolutions, will be addressed.

  15. Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

    Energy Technology Data Exchange (ETDEWEB)

    DALE, R.N.

    2000-05-01

    A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O & M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085.

  16. Development of a RF source for ITER NBI: First results with D- operation

    International Nuclear Information System (INIS)

    Speth, E.; Falter, H.D.; Franzen, P.; Heinemann, B.; Bandyopadhyay, M.; Fantz, U.; Kraus, W.; McNeely, P.; Riedl, R.; Tanga, A.; Wilhelm, R.

    2005-01-01

    As an alternative for ITER NBI a RF source is being developed at IPP, Garching. This paper reports the first results with deuterium extracted from a restricted extraction area and accelerated to about 22 KeV. A current density of 150 A/m 2 (calorimetric) of D - ions has been reached so far in a Cs-seeded discharge with an electron/ion ration of ≤1. The effect of the magnetic filter field on the yield and the electron suppression and possible limitations/improvements are discussed. The neutron production rate is about a factor 40 lower than expected from positive ions. Possible reasons for this are discussed

  17. Waste minimization, recycling and reuse in operations support services fleet maintenance

    International Nuclear Information System (INIS)

    Trego, A.L.

    1994-01-01

    Government regulations and smart business practices demand that organizations dramatically reduce both the type and volume of waste generated by their operations. This article describes successful waste minimization and recycling programs created by the Fleet Maintenance, Operations Support Services Division, Westinghouse Hanford Company. These comprehensive programs have greatly reduced waste formerly produced in maintaining 3,528 government-owned vehicles and nearly 200 emergency power generators at the Hanford Site. The actions are integral to preventing future contamination of the Site as well as to cleaning up the complexity of wastes from almost 50 years of defense production. The results of the Fleet Maintenance programs are impressive, recording cost savings of $290,000 in fiscal year 1993 and $965,000 since 1988

  18. Computerization of operation and maintenance for nuclear power plants. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. The technical document is the result of a series of advisory and consultant meetings held by the IAEA in Vienna in 1991 - 1994. The document was prepared with the participation of experts from Canada, France, Germany, Hungary, Japan, Russia, Sweden, United Kingdom, and the United States. Refs, figs and tabs

  19. Fuel Rod Consolidation Project: Phase 2, Final report: Volume 5, Operations and maintenance manual

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of this manual is to describe the function, installation, operation and maintenance of the Fuel Rod Consolidation System. This Document is preliminary and must be updated to incorporate any modifications to the mechanical and electrical systems that are performed during construction. Any changes and specific references related to the software requirements will be provided as the software is developed in Phase III. Setpoints related to equipment positions as a function of resolver and position transducer readings will also be provided in Phase III. References such as vendor supplied Operating and Maintenance Manuals for vendor components and assemblies are not available until a receipt of a purchase order. These references will become an integral part of this manual during the construction phase

  20. Applying the TOC Project Management to Operation and Maintenance Scheduling of a Research Vessel

    Science.gov (United States)

    Manti, M. Firdausi; Fujimoto, Hideo; Chen, Lian-Yi

    Marine research vessels and their systems are major assets in the marine resources development. Since the running costs for the ship are very high, it is necessary to reduce the total cost by an efficient scheduling for operation and maintenance. To reduce project period and make it efficient, we applied TOC project management method that is a project management approach developed by Dr. Eli Goldratt. It challenges traditional approaches to project management. It will become the most important improvement in the project management since the development of PERT and critical path methodologies. As a case study, we presented the marine geology research project for the purpose of operations in addition to repair on the repairing dock projects for maintenance of vessels.