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Sample records for cern-ps main power

  1. Supervision Application for the New Power Supply of the CERN PS (POPS)

    CERN Document Server

    Milcent, H; Gonzalez-Berges, M; Voitier, A

    2011-01-01

    The power supply system for the magnets of the CERN PS has been recently upgraded to a new system called POPS (POwer for PS). The old mechanical machine has been replaced by a system based on capacitors. The equipments as well as the low level controls have been provided by an external company (CONVERTEAM). The supervision application has been developed at CERN reusing the technologies and tools used for the LHC Accelerator and Experiments (UNICOS and JCOP frameworks, SIMATIC WinCC Open Architecture SCADA tool). The paper describes the full architecture of the control application, and the challenges faced for the integration with an outsourced system. The benefits of reusing the CERN industrial control frameworks and the required adaptations will be discussed. Finally, the initial operational experience will be presented.

  2. The MERIT High-Power Target Experiment at the CERN PS

    CERN Document Server

    McDonald, K T; Park, H; Tsang, T; Efthymiopoulos, I; Fabich, A; Haug, F; Lettry, J; Palm, M; Pereira, H; Mokhov, N; Striganov, S; Carroll, A J; Graves, V B; Spampinato, P T; Bennett, J R J; Caretta, O; Loveridge, P

    2010-01-01

    The MERIT (MER­cury In­tense Tar­get) ex­per­i­ment was run in the fall of 2007 using 14 and 24 GeV in­tense pro­ton beams from the CERN PS. It is a proof-of-prin­ci­ple ex­per­i­ment de­signed to val­i­date a tar­get con­cept for pro­duc­ing an in­tense muon source for a fu­ture muon col­lid­er or neu­tri­no fac­to­ry. The ex­per­i­ment suc­cess­ful­ly demon­strat­ed a tar­get tech­nique for mul­ti-MW pro­ton beams that uti­lizes a free-flow­ing liq­uid metal jet with­in the con­fines of a high-field solenoid. We de­scribe the ex­per­i­men­tal strat­e­gy and pa­ram­e­ters, as well as the re­sults ob­tained and their im­pli­ca­tions for fu­ture muon-based ac­cel­er­a­tor fa­cil­i­ties.

  3. Status of the Upgrade of the CERN PS Booster

    CERN Document Server

    Hanke, K; Angoletta, M; Bartmann, W; Bartolome, S; Benedetto, E; Bertone, C; Blas, A; Bonnal, P; Borburgh, J; Bozzini, D; Butterworth, A; Carli, C; Carlier, E; Cole, J; Dahlen, P; Delonca, M; Dobers, T; Findlay, A; Froeschl, R; Hansen, J; Hay, D; Jensen, S; Lacroix, J; Le Roux, P; Lopez Hernandez, L; Maglioni, C; Masi, A; Mason, G; Mathot, S; Mikulec, B; Muttoni, Y; Newborough, A; Nisbet, D; Olek, S; Paoluzzi, M; Perillo-Marcone, A; Pittet, S; Puccio, B; Raginel, V; Riffaud, B; Ruehl, I; Sarrió Martínez, A; Tan, J; Todd, B; Venturi, V; Weterings, W

    2013-01-01

    The CERN PS Booster (PSB) is presently undergoing an ambitious consolidation and upgrade program within the frame of the LHC Injectors Upgrade (LIU) project. This program comprises a new injection scheme for H- ions from CERN’s new Linac4, the replacement of the main RF systems and an energy upgrade of the PSB rings from 1.4 to 2 GeV which includes the replacement of the main magnet power supply as well as the upgrade of the extraction equipment. This paper describes the status and plans of this work program.

  4. CERN's PS Booster LLRF renovation : plans and initial beam tests

    CERN Document Server

    Angoletta, ME; Butterworth, A; Findlay, A; Leinonen, PM; Molendijk, JC; Pedersen, F; Sanchez-Quesada, J; Schokker, M

    2010-01-01

    In 2008 a project was started to renovate the CERN's PS Booster (PSB) low-level RF (LLRF). Required LLRF capabilities include frequency program, beam phase, radial and synchronization loops. The new LLRF will control the signals feeding the three RF cavities present in each ring; it will also shape the beam in a dual harmonic mode, operate a bunch splitting and create a longitudinal blow-up. The main benefits of this new LLRF are its full remote and cycle-to-cycle controllability, built-in observation capability and flexibility. The overall aim is to improve the robustness, maintainability and reliability of the PSB operation and to make it compatible with the injection from the future Linac4. This paper outlines the main characteristics of the software and hardware building blocks. Initial beam test results and hints on the main milestones and future work are also given.

  5. Process equipment data organisation in CERN PS controls

    International Nuclear Information System (INIS)

    Casalegno, L.; Cuperus, J.; Sicard, C.H.

    1990-01-01

    The CERN PS control system has a widely distributed architecture, mainly for fast response in a real-time environment. The organisation of the data for equipment access must be compatible with this architecture and give efficient program access to the data. Moreover, it must also offer managerial features such as data integrity, easy backup and restoration, adaptibility to changes in data structure, initialisation, data-entry facilities and automatic documentation. This paper shows how one can take advantage of a commercial data-base management system with its associated tools, adding to it some object-oriented programming concepts to meet the objectives of a manageable distributed data organisation having good run-time performance features and using a reasonable manpower investment. (orig.)

  6. Injection Bump Synchronization Study for the CERN PS

    CERN Document Server

    Serluca, Maurizio; Gilardoni, Simone; CERN. Geneva. ATS Department

    2016-01-01

    In the framework of the LHC Injector Upgrade (LIU) project the CERN PS injection kinetic energy will be upgraded from 1.4 to 2 GeV. The present injection bump is made by four bumpers in Straight Section (SS) 40, 42, 43, 44 and it will be converted in a five bumpers system to allow additional flexibility in the bump shape with a reduction of the proton losses during the bump closure. The injection section SS42 has being redesigned to accommodate a new eddy current septum which will host a new bumper magnet in the same vacuum vessel due to reduced longitudinal space availability. The synchronization and amplitude variation of the power converter of the in-vacuum bumper 42 with respect to the remaining outside vacuum bumpers 40, 41, 43, 44 can lead to orbit distortion and consequent losses during injection. In this note we present the experimental results from Machine Development (MD) studies along with simulations for the present system at 1.4 GeV to quantify the acceptable orbit distortion and the performance ...

  7. Linac4, a New Injector for the CERN PS Booster

    CERN Document Server

    Garoby, R; Gerigk, F; Hanke, K; Lombardi, A; Pasini, M; Rossi, C; Sargsyan, E; Vretenar, M

    2006-01-01

    The first bottle-neck towards higher beam brightness in the LHC injector chain is due to space charge induced tune spread at injection into the CERN PS Booster (PSB). A new injector called Linac4 is proposed to remove this limitation. Using RF cavities at 352 and 704 MHz, it will replace the present 50 MeV proton Linac2, and deliver a 160 MeV, 40 mA H- beam. The higher injection energy will reduce space charge effects by a factor of 2, and charge exchange will drastically reduce the beam losses at injection. Operation will be simplified and the beam brightness required for the LHC ultimate luminosity should be obtained at PS ejection. Moreover, for the needs of non-LHC physics experiments like ISOLDE, the number of protons per pulse from the PSB will increase by a significant factor. This new linac constitutes an essential component of any of the envisaged LHC upgrade scenarios. It is also designed to become the low energy part of a future 3.5 GeV, multi-megawatt superconducting linac (SPL). The present desig...

  8. Design of the New Wideband RF System for the CERN PS Booster

    CERN Document Server

    Paoluzzi, Mauro; Angoletta, Maria Elena; Arnaudon, Luca; Energico, Salvatore; Findlay, Alan; Haase, Matthias; Jaussi, Michael; Jones, Anthony; Landré, David; Molendijk, John; Quartullo, Danilo; Shaposhnikova, Elena

    2016-01-01

    For the renovation and upgrade of the CERN PS Booster (PSB) RF systems a development project was launched in 2012. The design, based on a new approach, aimed at replacing the existing tuned, narrowband RF systems with wideband, modular, solid-state driven units. A wide range of issues had to be addressed spanning from RF power production, radiation hardness of solid-state devices, active cancellation of beam-induced voltages, dedicated low-level electronics allowing multi-harmonic operation and beam stability. Following a three-year prototyping and testing campaign and two international reviews, the project endorsement came at the end of year 2015. It foresees the complete removal of present h1, h2 and h10 systems and the deployment of a new one covering all the frequency ranges from 1 MHz to 18 MHz. The four PSB rings will be equipped with 144 identical acceleration cells providing 24 kV total RF voltage per ring. This paper describes the design concepts, the retained solutions, the expected performances and...

  9. New Control Structure of the 200 MHz RF System in the CERN PS

    CERN Document Server

    Damerau, H; CERN. Geneva. AB Department

    2008-01-01

    The 200 MHz RF system is an essential tool for the preparation of high-intensity beams in the CERN PS. Presently, six RF cavities are operated to control the longitudinal bunch emittance and rebunching of the beam before the transfer to the SPS. Cavities are selected for the various processes with a dedicated hardware matrix, switching the individual timing pulses and voltage programs per cavity. However, the electronics used for the matrix hardware is obsolete and its reliability cannot be guaranteed due to a lack of spare modules and components. Instead of replacing the old hardware matrix by modern hardware, this note describes a new control structure for the 200MHz RF system so that no dedicated hardware will be required anymore. The implementation of the new control structure is based on two main concepts. Firstly, linked timing trees per blow-up or rebunching are used to handle all related timing and to store one row of the matrix. Secondly, as a reflection of the RF signal generation for the 200 MHz sy...

  10. New Control Structure of the 10 MHz RF System in the CERN PS

    CERN Document Server

    Damerau, H

    2013-01-01

    The 10MHz cavities comprise the main RF system in the CERN PS and the only one that allows acceleration. In total 11 tunable cavities (10 operational and a hot spare, grouped into 3+1 tuning groups and up to presently 6 voltage program groups) are distributed all around the circumference of the PS ring. Next to the RF drive signal each of the cavities is controlled by a voltage program and timing pulses to open and close the relays to short-circuit the cavity gaps. These control signals are presently generated by a dedicated hardware matrix. It translates voltage functions and relay timing pulses per cavity group into functions and timings per cavity. However, due to its central position in the RF beam control system, the dedicated hardware matrix can cause significant downtime in case of a major hardware failure. Instead of upgrading the existing obsolete hardware, this note suggests a replacement by standard controls hardware and dedicated application software. Thanks to advanced software concepts like “M...

  11. Rejuvenation of the controls of the CERN PS/ISOLDE facility using industrial components

    CERN Document Server

    Allard, J.; Locci, F.; Mornacchi, G.

    2001-01-01

    In the context of the general consolidation of the CERN ISOLDE facility, a project has been started to upgrade the ISOLDE control system. We describe the new ISOLDE control system, emphasizing the systematic use of industrial components such as PLCs and field buses, their integration with the existing, VME based, CERN PS control system and their potential applicability to both existing and new controls problems at the CERN PS complex. We also discuss how to extend a PLC-based solution to the case where real-time response is an issue.

  12. 3D Emittances Tailoring Techniques and Optimization with Space Charge for the Future CERN PS Booster Operations with Linac4

    CERN Document Server

    Forte, Vincenzo; Benedetto, Elena; Bracco, Chiara; Cieslak-Kowalska, Magdalena; Di Giovanni, Gian Piero

    2016-01-01

    In the frame of the LIU (LHC Injectors Upgrade) project, the CERN PS Booster is going to be renovated to host a new H⁻ charge-exchange injection from the Linac4. One important feature of the new injection scheme is the possibility to tailor a wide range of 3D emittances for CERN's different users in an intensity span in the order of 5·10⁹ to 1.6·10¹³ protons per PSB ring. This paper gives an overview of 3D multi-turn injection techniques, focusing on the future LHC beams, which aim at reaching high brightness, and on highest intensity beams (ISOLDE), where losses are the main concern. Complete RF capture simulations and transverse injection maps, including space charge effects, are presented and also intended to be used during the commissioning with Linac4.

  13. Upgraded DIRAC spectrometer at CERN PS for the investigation of pi pi and pi K atoms

    Czech Academy of Sciences Publication Activity Database

    Adeva, B.; Benelli, A.; Čechák, T.; Doškářová, P.; Hons, Zdeněk; Klusoň, J.; Lednický, Richard; Martinčík, J.; Průša, P.; Smolík, J.; Trojek, T.; Urban, T.; Vrba, T.

    2016-01-01

    Roč. 839, DEC (2016), s. 52-85 ISSN 0168-9002 R&D Projects: GA MŠk(CZ) LG13031 Institutional support: RVO:61389005 ; RVO:68378271 Keywords : upgraded DIRAC spectrometer * CERN PS * pi pi and pi K atoms * Life-time measurement * long-lived excited states of pi pi atoms Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders; BF - Elementary Particles and High Energy Physics (FZU-D) Impact factor: 1.362, year: 2016

  14. Simulation of Instability at Transition Energy with a New Impedance Model for CERN PS

    CERN Document Server

    Wang, Na; Biancacci, Nicolo; Migliorati, Mauro; Persichelli, Serena; Sterbini, Guido

    2016-01-01

    Instabilities driven by the transverse impedance are proven to be one of the limitations for the high intensity reach of the CERN PS. Since several years, fast single bunch vertical instability at transition energy has been observed with the high intensity bunch serving the neu-tron Time-of-Flight facility (n-ToF). In order to better understand the instability mechanism, a dedicated meas-urement campaign took place. The results were compared with macro-particle simulations with PyHEADTAIL based on the new impedance model developed for the PS. Instability threshold and growth rate for different longitu-dinal emittances and beam intensities were studied.

  15. Impedance studies of the dummy septum for CERN PS multi-turn extraction

    CERN Document Server

    Persichelli, S; Berrig, O; Herbst, J; Kuczerowski, J; Giovannozzi, M; Salvant, B

    2014-01-01

    A protection septum has been installed in the CERN PS section 15 in order to mitigate irradiation of the magnetic septum 16 for fast extractions towards the SPS. Impedance studies have been performed, showing that beams circulating in the septum during extraction generate sharp resonances in the coupling impedance. Impedance measurements with the wire technique have been performed, showing a good agreement with simulations. Instability rise times of trapped modes have been evaluated and compared to extraction duration. Solutions for reducing the impact on the stability of the beam have been considered

  16. Prospect for Charge Current Neutrino Interactions Measurements at the CERN-PS

    CERN Document Server

    Bernardini, P; Bozza, C; Brugnera, R; Cecchetti, A; Cecchini, S; Collazuol, G; Corso, F Dal; De Mitri, I; De Serio, M; Di Ferdinando, D; Dore, U; Dusini, S; Fabbricatore, P; Fanin, C; Fini, R A; Garfagnini, A; Grella, G; Kose, U; Laveder, M; Loverre, P; Longhin, A; Marsella, G; Mancarella, G; Mandrioli, G; Mauri, N; Medinaceli, E; Mezzetto, M; Muciaccia, M T; Orecchini, D; Paoloni, A; Pastore, A; Patrizii, L; Pozzato, M; Rescigno, R; Rosa, G; Simone, S; Sioli, M; Sirri, G; Spurio, M; Stanco, L; Stellacci, S; Surdo, A; Tenti, M; Togo, V

    2011-01-01

    Tensions in several phenomenological models grew with experimental results on neutrino/antineutrino oscillations at Short-Baseline (SBL) and with the recent, carefully recomputed, antineutrino fluxes from nuclear reactors. At a refurbished SBL CERN-PS facility an experiment aimed to address the open issues has been proposed [1], based on the technology of imaging in ultra-pure cryogenic Liquid Argon (LAr). Motivated by this scenario a detailed study of the physics case was performed. We tackled specific physics models and we optimized the neutrino beam through a full simulation. Experimental aspects not fully covered by the LAr detection, i.e. the measurements of the lepton charge on event-by-event basis and their energy over a wide range, were also investigated. Indeed the muon leptons from Charged Current (CC) (anti-)neutrino interactions play an important role in disentangling different phenomenological scenarios provided their charge state is determined. Also, the study of muon appearance/disappearance ca...

  17. A Directory Service for the CERN PS/SL Java Programming Interface

    International Nuclear Information System (INIS)

    Cuperus, J.; Charrue, P.; DiMaio, F.; Kostro, K.; Watson, W.

    1999-01-01

    The CERN PS and SL accelerator control groups developed a common application programming interface (API) in Java [1]. Part of this API is a directory service that provide information about the underlying hardware and software. With this information, it is possible to write generic programs that do general actions on lists of devices without hard coding of device names. And, starting from a device name, full details about related devices, the device itself and its class and properties, can be obtained, including the meaning of bits and bit-patterns in status words. The interface definition is independent of any implementation but a reference implementation is provided using Java Database Connectivity (JDBC) against a set of tables in a relational database. Data from very different systems can be brought together and presented in a uniform way to the user. The full potential of the directory service is reached when it is used in software components (Java Beans)

  18. Engineering a large application software project: the controls of the CERN PS accelerator complex

    International Nuclear Information System (INIS)

    Benincasa, G.P.; Daneels, A.; Heymans, P.; Serre, Ch.

    1985-01-01

    The CERN PS accelerator complex has been progressively converted to full computer controls without interrupting its full-time operation (more than 6000 hours per year with on average not more than 1% of the total down-time due to controls). The application software amounts to 120 man-years and 450'000 instructions: it compares with other large software projects, also outside the accelerator world: e.g. Skylab's ground support software. This paper outlines the application software structure which takes into account technical requirements and constraints (resulting from the complexity of the process and its operation) and economical and managerial ones. It presents the engineering and management techniques used to promote implementation, testing and commissioning within budget, manpower and time constraints and concludes with experience gained

  19. Production of strange particles in antineutrino interactions at the CERN PS

    CERN Document Server

    Erriquez, O; Bisi, V; Bonetti, S; Bonneaud, G; Bullock, F W; Cavalli, D; Escoubés, B; Fogli-Muciaccia, M T; Franzinetti, Carlo; Gamba, D; Guyonnet, J L; Halsteinslid, A; Huss, D; Jarlskog, C; Jones, T W; Marzari-Chiesa, A; Michette, A G; Myklebost, K; Natali, S; Nuzzo, S; Paty, M; Pullia, A; Racca, C; Riccati, L; Riester, J L; Rognebakke, A; Rollier, M; Romero, A; Sacco, R; Schäffer, M; Skjeggestad, O; Tvedt, B

    1978-01-01

    The authors have studied neutral strange particle production in the bubble chamber Gargamelle filled with propane and exposed to antineutrinos from the CERN PS. Cross sections are presented for Lambda , Sigma /sup 0/ and K/sup 0/ production. Associated production reactions ( Delta S=0) have been observed in the charged and the neutral current channels. From 45 candidates for the quasi-elastic reaction nu p to mu /sup +/ Lambda , on bound and free protons, estimates of the axial transition form factor M/sub A/ have been made using the total cross section and the t distribution. The weighted average from the two methods is M/sub A/=862+or-190 MeV. From a subsample of 15 candidates for nu interactions on free protons in propane, with (28+or-6)% background from nu interactions on bound protons, M/sub A/=883+or-243 MeV is obtained. The polarization of the Lambda hyperons has been studied for the quasi-elastic reaction. (11 refs).

  20. Injection septa position and angle optimisation in view of the 2 GeV liu upgrade of the CERN PS

    CERN Document Server

    Serluca, HM; Forte, V; Fraser, M; Sterbini, G

    2017-01-01

    In the framework of the LHC Injector Upgrade (LIU)project the CERN PS injection kinetic energy will be up-graded from 1.4 to 2 GeV. The injection equipment, whichis already operating close to its limit, is being redesigned tocope with 30% increase in the beam rigidity. In this paper wepresent the experimental results from Machine Development(MD) studies on the present septum to explore its operationalhardware limits with respect to aperture restrictions, beamlosses and kick strengths in view of the LIU upgrade

  1. Numerical Simulations to Evaluate the Performance of CERN PS Dummy Septum to Reduce Irradiation for the Multi-Turn Extraction

    CERN Document Server

    Hernalsteens, C; Gilardoni, S; Giovannozzi, M

    2013-01-01

    The losses created by the proposed Multi-Turn Extraction (MTE) at the CERN PS induce high activation of the magnetic extraction septum due to the de-bunched longitudinal beam structure requested to transfer the beam to the SPS. A mitigation measure is under study aiming at localizing the losses in a well-shielded area by shadowing the magnetic extraction septum thanks to a septum-like passive device. Such a solution is based on a so-called dummy septum, a blade which absorbs particles during the rise time of the extraction kickers for MTE beams. The efficiency of the scheme is presented in this paper. The quantitative estimate is based on detailed simulations that analyze the beam-matter interaction and provide a determination of the shadowing effect of the dummy septum.

  2. Feasibility study of a 2 GeV superconducting $H^{-}$ linac as injector for the CERN PS

    CERN Document Server

    Garoby, R; Hill, C E; Lombardi, A M; Ostroumov, P N; Tessier, J M; Vretenar, Maurizio

    1998-01-01

    This preliminary feasibility study is based on the availability of the CERN LEP2 superconducting RF system after LEP de-commissioning. The option that is explored is to use this system as part of a high energy H- linac injecting at 2 GeV into the CERN PS, with the aim of reliably providing at its output twice the presently foreseen transverse beam brightness at the ultimate intensity envisaged for LHC. This requires the linac to be pulsed at the PS repetition rate of 0.8 Hz with a mean beam current of 10 mA which is sufficient for filling the PS in 240 ms (i.e. about 100 turns) with the ultimate intensity foreseen for injection for the LHC. The linac is composed of two RFQs with a chopping section, a room temperature DTL, a superconducting section with reduced beta cavities up to 1 GeV, and a section of LEP2 cavities up to 2 GeV. This study deals, in particular, with the problems inherent in H- acceleration up to high energy and in the pulsed operation of SC cavities. Means for compensating microphonic vibrat...

  3. Upgraded DIRAC spectrometer at CERN PS for the investigation of ππ and πK atoms

    Energy Technology Data Exchange (ETDEWEB)

    Adeva, B. [Santiago de Compostela University (Spain); Afanasyev, L. [JINR, Dubna (Russian Federation); Allkofer, Y. [Zurich University (Switzerland); Amsler, C. [Albert Einstein Centre for Fundamental Physics, Laboratory of High Energy Physics, Bern (Switzerland); Anania, A. [INFN, Sezione di Trieste and Messina University, Messina (Italy); Aogaki, S. [IFIN-HH, National Institute for Physics and Nuclear Engineering, Bucharest (Romania); Benelli, A. [Czech Technical University in Prague (Czech Republic); Brekhovskikh, V. [IHEP, Protvino (Russian Federation); Caragheorgheopol, Gh. [IFIN-HH, National Institute for Physics and Nuclear Engineering, Bucharest (Romania); Cechak, T. [Czech Technical University in Prague (Czech Republic); Chiba, M. [Tokyo Metropolitan University (Japan); Chliapnikov, P. [IHEP, Protvino (Russian Federation); Ciocarlan, C.; Constantinescu, S. [IFIN-HH, National Institute for Physics and Nuclear Engineering, Bucharest (Romania); Detraz, C. [CERN, Geneva (Switzerland); Doskarova, P. [Czech Technical University in Prague (Czech Republic); Drijard, D. [CERN, Geneva (Switzerland); Dudarev, A. [JINR, Dubna (Russian Federation); Duma, M.; Dumitriu, D. [IFIN-HH, National Institute for Physics and Nuclear Engineering, Bucharest (Romania); and others

    2016-12-11

    The DIRAC spectrometer installed at CERN PS was upgraded in order to study simultaneously A{sub 2π} and A{sub πK} atoms, namely the bound states of two π mesons, and of π and K mesons, respectively. The detector system can now accept a high intensity beam of 2–6×10{sup 11} primary protons per second. The electronics and the data-acquisition system can handle a very large amount of data to identify π, K, p, e and µ, allowing the selection of ππ and πK pairs in the offline analysis. The resolution of the longitudinal and transverse components of the relative momentum Q of each meson pair in their center-of-mass system with respect to the direction of the pair was substantially improved. The analysis of their distributions allowed an reliable separation between the meson pairs originating from hadronic atoms and the backgrounds permitting the measurement of the lifetimes of hadronic atoms in the ground state and π–π, π–K s-wave scattering lengths. The upgraded setup also allowed the study of the long-lived excited states of ππ atoms.

  4. The Proton Beams for the New Time-of-Flight Neutron Facility at the CERN-PS

    CERN Document Server

    Cappi, R; Métral, G

    2000-01-01

    The experimental determination of neutron cross sections in fission and capture reactions as a function of the neutron energy is of primary importance in nuclear physics. Recent developments at CERN and elsewhere have shown that many fields of research and development, such as the design of Accelerator-Driven Systems (ADS) for nuclear waste incineration, nuclear astrophysics, fundamental nuclear physics, dosimetry for radiological protection and therapy, would benefit from a better knowledge of neutron cross sections. A neutron facility at the CERN-PS has been proposed with the aim of carrying out a systematic and high resolution study of neutron cross sections through Time-Of-Flight (n-TOF) measurement. The facility requires a high intensity proton beam (about 0.7x1013 particles/bunch) distributed in a short bunch (about 25 ns total length) to produce the neutrons by means of a spallation process in a lead target. To achieve these characteristics, a number of complex beam gymnastics have to be performed. All...

  5. A New High-intensity Proton Irradiation Facility at the CERN PS East Area

    CERN Document Server

    Gkotse, B; Lima, P; Matli, E; Moll, M; Ravotti, F

    2014-01-01

    and IRRAD2), were heavily and successfully used for irradiation of particle detectors, electronic components and materials since 1992. These facilities operated with particle bursts - protons with momentum of 24GeV/c - delivered from the PS accelerator in “spills” of about 400ms (slow extraction). With the increasing demand of irradiation experiments, these facilities suffered from a number of restrictions such as the space availability, the maximum achievable particle flux and several access constraints. In the framework of the AIDA project, an upgrade of these facilities has been realized during the CERN long shutdown (LS1). While the new proton facility (IRRAD) will continue to be mainly devoted to the radiation hardness studies for the High Energy Physics (HEP) experimental community, the new mixed-field facility (CHARM) will mainly host irradiation experiments for the validation of electronic systems used in a...

  6. Control protocol: large scale implementation at the CERN PS complex - a first assessment

    International Nuclear Information System (INIS)

    Abie, H.; Benincasa, G.; Coudert, G.; Davydenko, Y.; Dehavay, C.; Gavaggio, R.; Gelato, G.; Heinze, W.; Legras, M.; Lustig, H.; Merard, L.; Pearson, T.; Strubin, P.; Tedesco, J.

    1994-01-01

    The Control Protocol is a model-based, uniform access procedure from a control system to accelerator equipment. It was proposed at CERN about 5 years ago and prototypes were developed in the following years. More recently, this procedure has been finalized and implemented at a large scale in the PS Complex. More than 300 pieces of equipment are now using this protocol in normal operation and another 300 are under implementation. These include power converters, vacuum systems, beam instrumentation devices, RF equipment, etc. This paper describes how the single general procedure is applied to the different kinds of equipment. The advantages obtained are also discussed. ((orig.))

  7. The Merit(nTOF-11) High Intensity Liquid Mercury Target Experiment at the CERN PS

    CERN Document Server

    Efthymiopoulos, I; Caretta, O; Carroll, A J; Fabich, A; Graves, V B; Grudiev, A; Haug, F; Kirk, H G; Lettry, Jacques; Loveridge, P; McDonald, K T; Mokhov, N; Palm, M; Park, H; Pernegger, H; Spampinato, P T; Steerenberg, R; Striganov, S; Tsang, T

    2008-01-01

    The MERIT(nTOF-11) experiment is a proof-ofprinciple test of a target system for a high power proton beam to be used as front-end for a neutrino factory or a muon collider. The experiment took data in autumn 2007 with the fast-extracted beam from the CERN Proton Synchrotron (PS) to a maximum intensity of $30 × 10^{12}$ per pulse. The target system, based on a free mercury jet, is capable of intercepting a 4-MW proton beam inside a 15-T magnetic field required to capture the low energy secondary pions as the source for intense muon beams. Partice detectors installed around the target setup measure the secondary particle flux out of the target and can probe cavitation effects in the mercury jet when excited by an intense proton beam.Preliminary results of the data analysis will be presented here.

  8. MERIT - The high intensity liquid mercury target experiment at the CERN PS

    CERN Document Server

    Efthymiopoulos, I

    2009-01-01

    The MERIT experiment is a proof-of-principle test of a target system for high power proton beams to be used as front-end for a Neutrino Factory complex or a Muon Collider. The experiment took data in autumn 2007 with the fast extracted beam from the CERN Proton Synchrotron (PS) to a maximum intensity of about 30 × 1012 protons per pulse. The target system, based on a free mercury jet, allowed investigation of the interseption of a 4-MW proton beam inside a 15-T magnetic field required to capture the low-energy secondary pions as the source of the required intense muon beams. Particle detectors have been installed around the target setup to measure the secondary particle flux out of the target and probe cavitation effects in the mercury jet when exited with a beam of variable intensity. With the analysis of the data ongoing, results will be presented here that demonstrate the validity of the liquid target concept.

  9. Intensity effects in the formation of stable islands in phase space during the multi-turn extraction process at the CERN PS

    CERN Document Server

    Machida, Shinji; Prior, Chris; Gilardoni, Simone; Giovannozzi, Massimo; Hirlander, Simon; Huschauer, Alexander

    2016-01-01

    The CERN PS utilises a Multi-Turn Extraction (MTE) scheme to stretch the beam pulse length to optimise the filling process of the SPS. MTE is a novel technique to split a beam in transverse phase space into nonlinear stable islands. The recent experimental results indicate that the positions of the islands depend on the total beam intensity. Particle simulations have been performed to understand the detailed mechanism of the intensity dependence. The analysis carried out so far suggests space charge effects through image charges and image currents on the vacuum chamber and the magnets iron cores dominate the observed behaviour. In this talk, the latest analysis with realistic modelling of the beam environment is discussed and it is shown how this further improves the understanding of intensity effects in MTE.

  10. Nuclear power station main control room habitability

    International Nuclear Information System (INIS)

    Paschal, W.B.; Knous, W.S.

    1989-01-01

    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

  11. Isolated systems with wind power. Main report

    DEFF Research Database (Denmark)

    Lundsager, P.; Bindner, Henrik W.; Clausen, Niels-Erik

    2001-01-01

    The overall objective of this research project is to study the development of methods and guidelines rather than "universal solutions" for the use of wind energy in isolated communities. The main specific objective of the project is to develop and present amore unified and generally applicable...... approach for assessing the technical and economical feasibility of isolated power supply systems with wind energy. As a part of the project the following tasks were carried out: Review of literature, fieldmeasurements in Egypt, development of an inventory of small isolated systems, overview of end...... for Isolated Systems with Wind Power, applicable for international organisations such as donoragencies and development banks....

  12. Isolated systems with wind power. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Lundsager, P.; Bindner, H.; Clausen, N.E.; Frandsen, S.; Hansen, L.H.; Hansen, J.C.

    2001-06-01

    The overall objective of this research project is to study the development of methods and guidelines rather than 'universal solutions' for the use of wind energy in isolated communities. The main specific objective of the project is to develop and present a more unified and generally applicable approach for assessing the technical and economical feasibility of isolated power supply systems with wind energy. As a part of the project the following tasks were carried out: Review of literature, field measurements in Egypt, development of an inventory of small isolated systems, overview of end-user demands, analysis of findings and development of proposed guidelines. The project is reported in one main report and four topical reports, all of them issued as Risoe reports. This is the Main Report Risoe-R-1256, summing up the activities and findings of the project and outlining an Implementation Strategy for Isolated Systems with Wind Power, applicable for international organisations such as donor agencies and development banks. (au)

  13. CBA main magnet power supply ripple reduction

    International Nuclear Information System (INIS)

    Bagley, G.; Edwards, R.J.

    1983-01-01

    The preliminary results of a development program to minimize beam perturbation resulting from ripple current generated by the CBA Main Magnet Power Supply are presented. The assessment of the magnitude and causes of the ripple generated led to a modification of the SCR Gate Driver and the addition of a bandpass amplifier correction loop which gave significant improvement. A description of the changes made and the results obtained are included. A second design approach was developed in which the timing of the SCR gate pulses is directly determined by a VCO. The results reported with this VCO Loop indicate superior performance particularly at frequencies below 60 Hz. A shunt transistor regulator design is proposed to minimize higher SCR switching frequency harmonics

  14. The AGS main magnet power supply upgrade

    International Nuclear Information System (INIS)

    Sandberg, J.N.; Casella, R.; Geller, J.; Marneris, I.; Soukas, A.; Schumburg, N.

    1995-01-01

    The AGS Main Magnet Power Supply consists of a group of thyristor controlled power converters that operate from full rectify to full invert. In order to minimize ripple during the critical periods of injection and extraction 24 pulse converters are used for these portions of the cycle. The maximum voltage available in this mode is nominally 2,000 volts. The converters that are functional during this portion of the cycle are called the flat-top bank or ''F'' bank modules. During acceleration and invert where voltages of up to 12,000 volts are needed and where the ripple requirements are less stringent, groups of twelve pulse converters are operational. These converters are called the Pulsed bank or ''P'' bank modules. The original controlled rectifier system consisted of 96 large mercury filled excitron tubes divided equally between the P bank and F bank converters. These devices were extremely durable and ran successfully for over twenty years. It was, decided to replace the excitron farm with multiple arrangements of three-phase, full-wave, bridge modules that utilize silicon controlled rectifiers (SCR's or thyristors) as the switching element. In order to match the existing transformer connections and buswork, eight identical modules were required; four for the P bank system and four for the F bank system. In order to reduce noise pickup and provide electrical isolation the high level SCR gate triggers are provided via fiberoptic cable. The status of various parameters such as water flow, auxiliary power supply performance, trigger circuitry failure, over voltage, overcurrent, and loss of phase reference are monitored via a programmable logic controller (PLCs). The PLCs use isolated input and output modules for various voltage levels from TTL to 150 Vdc to 125 Vac. These devices are extremely flexible and have allowed modifications and improvements that have enhanced the performance over any equivalent hard wired system

  15. Design of Injection and Extraction Systems with Optimisation of Lattice and Layout for the CERN PS2 Synchrotron

    CERN Document Server

    Bartmann, W

    2009-01-01

    The CERN Proton Synchrotron PS2 is one of the foreseen accelerators for the LHC injector upgrade. This upgrade aims first at increasing the instantaneous luminosity of LHC and second at providing a reliable beam for the CERN accelerator complex. From this aspect, the main characteristics of the PS2 are high reliability for high intensity beams. The goal of this thesis was the design of the machine’s lattice and injection/extraction systems meeting the constraints coming mainly from the LHC beam type but also from beam requirements of experiments at PS2 and the SPS. In the design, the given energy range together with filling schemes for different beam types and RF cogging were first used to define the circumference of the machine. Estimates on the space requirements of injection/extraction systems were made in order to divide the total machine length between arc and long straight section. Existing tunnels for transfer lines together with the minimisation of the total transfer line length favoured a race trac...

  16. Maine Tidal Power Initiative: Environmental Impact Protocols For Tidal Power

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Michael Leroy [Univ. of Maine, Orono, ME; Zydlewski, Gayle Barbin [Univ. of Maine, Orono, ME; Xue, Huijie [Univ. of Maine, Orono, ME; Johnson, Teresa R. [Univ. of Maine, Orono, ME

    2014-02-02

    The Maine Tidal Power Initiative (MTPI), an interdisciplinary group of engineers, biologists, oceanographers, and social scientists, has been conducting research to evaluate tidal energy resources and better understand the potential effects and impacts of marine hydro-kinetic (MHK) development on the environment and local community. Project efforts include: 1) resource assessment, 2) development of initial device design parameters using scale model tests, 3) baseline environmental studies and monitoring, and 4) human and community responses. This work included in-situ measurement of the environmental and social response to the pre-commercial Turbine Generator Unit (TGU®) developed by Ocean Renewable Power Company (ORPC) as well as considering the path forward for smaller community scale projects.

  17. Production of high power microwaves for particle acceleration with an FEL bunched electron beam

    CERN Document Server

    Gardelle, J; Marchese, G; Padois, M; Rullier, J L; Donohue, J T

    1999-01-01

    Among the studies in the framework of high gradient linear electron-positron collider research, the Two-Beam Accelerator (TBA) is a very promising concept, and two projects are in progress, the Compact Linear Collider project at CERN (W. Schnell, Report no. CERN SL/92-51 and CLIC note 184; K. Huebner, CERN/PS 92-43, CLIC note 176; S. Van der Meer, CERN/PS 89-50, CLIC note 97.) and the Relativistic Klystron-TBA project at LBNL (Technical Review Committee, International Linear Collider Technical Review Committee Report 1995, SLAC-R-95-471, 1995). In a TBA an extremely intense low-energy electron beam, called the drive beam, is bunched at the desired operating frequency, and upon passing through resonant cavities generates radio-frequency power for accelerating the main beam. Among the different approaches to the production of a suitable drive beam, the use of an FEL has been proposed and is under active study at CEA/CESTA.

  18. Motor-Generator powering the PS (Proton Synchrotron) main magnets

    CERN Multimedia

    1983-01-01

    This motor-generator,30 MW peak, 1500 r.p.m.,pulsed power supply for the PS main magnet replaced in 1968 the initial 3000 r.p.m. motor-generator-flywheel set which had served from the PS start-up in 1959 until end 1967. See also photo 8302337 and its abstract.

  19. Main unit electrical protection at Sizewell 'B' power station

    International Nuclear Information System (INIS)

    Fischer, A.; Keates, T.

    1992-01-01

    For any power station, reliable electrical protection of the main generating units (generators plus generator transformers) has important commercial implications. Spurious trips cause loss of generation and consequent loss of revenue, while failure to rapidly isolate a fault leads to unnecessary damage and again, loss of generation and revenue. While these conditions apply equally to Sizewell B there are additional factors to be taken into consideration. A spurious trip of a main generating unit may lead to a trip of the reactor with an associated challenge to the shutdown and core cooling plant. The generator transformers, besides exporting power from the generators to the 400 kV National Grid, also import power from the Grid to the 11 kV Main Electrical System, which in turn is the preferred source of supply to the Essential Electrical System. The Main Unit Protection is designed to clear generator faults leaving this off-site power route intact. Hence failure to operate correctly could affect the integrity of the Essential Electrical Supplies. (Author)

  20. Main building of the Paks nuclear power plant, Hungary

    International Nuclear Information System (INIS)

    Fejes, A.

    1983-01-01

    The general layout of the main service building of the power plant, the applied building materials as well as the prefabricated structures are described. The conditions of planning and construction are discussed. Novel construction methods under the given conditions were utilized. (author)

  1. Analysis of main dynamic parameters of split power transmission

    Directory of Open Access Journals (Sweden)

    A. Janulevičius

    2008-06-01

    Full Text Available The review carried out had shown one basic approach of split power transmission to the organization of drive which is applied to stepless transmissions of tractors and parallel hybrid cars. In the split power transmission the power split device uses a planetary gear. Tractor engine power in the split power transmission is transmitted to the drive shaft via a mechanical and hydraulic path. The theoretical analysis of main parameters of the split power transmission of the tractor is presented. The angular velocity of sun and coronary gears of the differential set is estimated by solution of the system of equations in which one equation is made for planetary differential gear, and another – for hydrostatic drive. The analysis of the transmission gear-ratio dependencies on the ratio of hydraulic machines capacities is carried out. Dependence of the variation of angular velocity of the coronary and the sun gears on the ground speed of the tractor is presented. Dependence of sum shaft torque and its constituents, carried by mechanical and hydraulic lines, on sum shaft angular velocity and ground speed of tractor and engine speed is also presented.

  2. The AGS Booster main ring power supply system

    International Nuclear Information System (INIS)

    Soukas, A.; Hughes, K.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

    1989-01-01

    The AGS Booster is being designed as a very versatile particle accelerator. Its primary function is to be a high quality injector to the currently operating Alternating Gradient Synchrotron (AGS). The Booster/AGS combination will produce proton intensities greater than 5 x 10 13 protons per pulse (ppp), and accelerate heavy ions, with mass up to 200, to a maximum energy of 15 GeV per atomic mass unit (GeV/amu). The power supply for the Booster Main Ring (BMRPS) has to accommodate a wide range of cycles and a wide range of operating parameters. The cycles range from storage for several seconds to rapid cycling at 7.5 Hz. The peak output power is 18 MW. This paper will describe the AGS Booster machine powering requirements, the choice of power supply, the a.c. circuit tie-in and its associated problems and some of the details of the design of the BMRPS. 9 refs., 2 figs

  3. Power demand operation - environment and potential. Proposals for main project

    International Nuclear Information System (INIS)

    Wathne, M.

    1995-01-01

    This report discusses proposals for a main project on environmental and other problems arising when hydroelectric power stations supply energy at gigawatt levels. The project aims in particular to identify environmental problems where too little is known today for proper planning of this type of operation. The proposals emphasize the consequences which cannot be adequately analysed in terms of current techniques. These techniques presuppose steady state conditions. One proposal concerns market terms for power sales. Other proposals deal with hydrological data and uncertainty, capacity of watercourses, ice and temperature, aquatic eco-systems, erosion, supersaturation of water with air, flooding and dam breaks, impact on climate, inflow of fresh water in fjords and impact on algae. 33 refs., 4 tabs

  4. A High Resolution Spallation Driven Facility at the CERN-PS to Measure Neutron Cross Sections in the Interval from 1 eV to 250 MeV a Relative Performance Assessment

    CERN Document Server

    Rubbia, Carlo; Bouvet-Bensimon, D; Buono, S; Cappi, R; Cennini, P; Gelès, C; Goulas, I; Kadi, Y; Pavlopoulos, P; Revol, Jean Pierre Charles; Tzima, A; Vlachoudis, V

    1998-01-01

    In the proposed facility with 24 GeV PS beam on a Lead target, the number of produced neutrons exceeds 760 per proton. In comparison, with a LINAC (GELINA) one currently obtains only about 0.05 neutrons per electron of about 100 MeV. An additional factor of 2.5 for the CERN facility is due to the strong, forward peaking of the neutron flux, arising from the high proton energy and corresponding longitudinal boost. This huge factor in neutron yield per incident particle, namely 2.5 x 760/0.05 = 3.8 x 10^4, is only partially off-set by the higher, time averaged current of the LINAC e.g. 100 mA vs . 2 mA of the CERN-PS. Therefore the useful, initial neutron rate at the CERN facility is about three orders of magnitude larger than in the most performing electron LINAC’s, GELINA in Belgium and ORELLA in the US. The time duration of the PS pulse is presently Deltat|_r.m.s.=13.5 ns and we believe it could be reduced to Deltat|_r.m.s.= 6.75 ns. The electron LINAC has much shorter pulses Deltat| _r.m.s.= 1 ns, to which...

  5. TQC works in newly-built nuclear power plant and main electric power system plannings

    International Nuclear Information System (INIS)

    Akiyama, Yoshihisa; Kawakatsu, Tadashi; Hashimoto, Yasuo

    1985-01-01

    In the Kansai Electric Power Co., Inc., TQC has been introduced to solve such major problems in nuclear power generation as the securing of nuclear power reliability, the suppression of rises in the costs, the reduction in long periods of power failure and the promotion in siting of nuclear power plants. It is thus employed as a means of the ''creation of a slim and tough business constitution''. The state of activities in Kansai Electric are described in quality assurance of a newly-built nuclear power plant and in raising the reliability of the main electric power system to distribute the generated nuclear power and further the future prospects are explained. (Mori, K.)

  6. Power grid, mains filtering and power line communications ... a root cause for incompatibilities

    NARCIS (Netherlands)

    Coenen, Mart

    2013-01-01

    The power grid is intentionally meant to distribute electrical energy at the mains frequency, as produced by the electricity generating plants, towards the end-users. The three-phase low-voltage distribution network can be utilized more efficiently when a power factor of 1 is achieved and no

  7. High Precision Current Control for the LHC Main Power Converters

    CERN Document Server

    Thiesen, H; Hudson, G; King, Q; Montabonnet, V; Nisbet, D; Page, S

    2010-01-01

    Since restarting at the end of 2009, the LHC has reached a new energy record in March 2010 with the two 3.5 TeV beams. To achieve the performance required for the good functioning of the accelerator, the currents in the main circuits (Main Bends and Main Quadrupoles) must be controlled with a higher precision than ever previously requested for a particle accelerator at CERN: a few parts per million (ppm) of nominal current. This paper describes the different challenges that were overcome to achieve the required precision for the current control of the main circuits. Precision tests performed during the hardware commissioning of the LHC illustrate this paper.

  8. Local election: does bureaucracy become one of main political power?

    Science.gov (United States)

    Amin, Muryanto; Musthafa Sembiring, Walid

    2018-03-01

    This writing aims to analyze the emergence of bureaucracy as one of political power in local level after the local election is held in Indonesia. Due to information authorization, media network, and stable structure, the bureaucracy soon transforms into political power which can compete with the other political power at the local level. In Medan local election in 2010 and 2015 has evidently proven the power of bureaucracy network in winning the bureaucrat-background candidates. As methods of the research, the researcher held a Focus-Group Discussion (FGD) and had an in-depth interview with ten bureaucracy elites in Medan and local political elites. The observation and Focus-Group Discussion (FGD) are analyzed using qualitative analysis technique typology. The result states that the bureaucracy network in Medan has been used in a massive way as the political power of winning. The structure of bureaucracy – from the top to the low – is involved in the winning. The most governmental programs were applied to attract the mass’ sympathy toward the candidates. The bureaucratic proximity to media network is also used to do a campaign in a massive way. The conclusion of the research is that bureaucracy emerges as a new, massive, effective local political power in the local election.

  9. Increasing power distribution mains efficiency through new mains configurations; Effizienzsteigerung im Verteilnetz durch neue Netzkonfigurationen

    Energy Technology Data Exchange (ETDEWEB)

    Hoeckel, M.

    2005-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) summarises the findings of a study that sought to find new approaches to minimise distribution losses in medium and low voltage power grids. Options examined included the optimisation of distribution-station density, increasing the nominal voltage of the low-voltage grid and the implementation of decentralised energy production. Data from real-life grids were used together with simulations to analyse possible solutions. The conclusions of these analyses are presented and discussed. In addition, qualitative and detailed examinations were made concerning grid quality factors such as availability and voltage stability.

  10. Transient behaviour of main coolant pump in nuclear power plants

    International Nuclear Information System (INIS)

    Delja, A.

    1986-01-01

    A basic concept of PWR reactor coolant pump thermo-hydraulic modelling in transient and accident operational condition is presented. The reactor coolant pump is a component of the nuclear steam supply system which forces the coolant through the reactor and steam generator, maintaining design heat transfer condition. The pump operating conditions have strong influence on the flow and thermal behaviour of NSSS, both in the stationary and nonstationary conditions. A mathematical model of the reactor coolant pump is formed by using dimensionless homologous relations in the four-quadrant regimes: normal pump, turbine, dissipation and reversed flow. Since in some operational regimes flow of mixture, liquid and steam may occur, the model has additional correction members for two-phase homologous relations. Modular concept has been used in developing computer program. The verification is performed on the simulation loss of offsite power transient and obtained results are presented. (author)

  11. The main pump motor remote visual check in the application of the domestic nuclear power plants

    International Nuclear Information System (INIS)

    Ge Lianwei; Yu Tao; Fang Jiang; Zhang Ting; Zhang Xingtian; Ding Youyuan

    2014-01-01

    In this paper, the Qinshan nuclear power station the first main pump motor to the successful implementation of remote visual inspection the main pump motor remote visual inspection applications. Qinshan Nuclear Power Plant Units 1 and 2 of the main pump motor inspection results show that the key components of the Qinshan Nuclear Power Plant Units 1 and 2 of the main pump rotor, stator end coils good condition, its problems for 10 years in the motor does not affect the normal use of the motor state disintegration overhaul problems tracking disintegration overhaul in 10 years. (authors)

  12. The simulation of control system for the KEK main ring power supply, 1

    International Nuclear Information System (INIS)

    Sato, Hikaru; Shintomi, Takakazu; Kubo, Tadashi; Masuda, Masayoshi; Nakano, Michio.

    1975-09-01

    The simulation of control system for the KEK main ring power supply is performed. The inductance of the magnet is assumed to be linear against to the current. The results of the simulations are described. (auth.)

  13. 20 kHz main inverter unit. [for space station power supplies

    Science.gov (United States)

    Hussey, S.

    1989-01-01

    A proof-of-concept main inverter unit has demonstrated the operation of a pulse-width-modulated parallel resonant power stage topology as a 20-kHz ac power source driver, showing simple output regulation, parallel operation, power sharing and short-circuit operation. The use of a two-stage dc input filter controls the electromagnetic compatibility (EMC) characteristics of the dc power bus, and the use of an ac harmonic trap controls the EMC characteristics of the 20-kHz ac power bus.

  14. Booster main magnet power supply, present operation and potential future upgrades

    Energy Technology Data Exchange (ETDEWEB)

    Bajon, E.; Bannon, M.; Marneris, I.; Danowski, G.; Sandberg, J.; Savatteri, S.

    2011-03-28

    The Brookhaven Booster Main Magnet Power Supply (MMPS) is a 24 pulse thyristor control supply, rated at 5500 Amps, +/-2000 Volts, or 3000 Amps, +/-6000 Volts. The power supply is fed directly from the power utility and the peak magnet power is 18 MWatts. This peak power is seen directly at the incoming ac line. This power supply has been in operation for the last 18 years. This paper will describe the present topology and operation of the power supply, the feedback control system and the different modes of operation of the power supply. Since the power supply has been in operation for the last 18 years, upgrading this power supply is essential. A new power supply topology has been studied where energy is stored in capacitor banks. DC to DC converters are used to convert the dc voltage stored in the capacitor banks to pulsed DC voltage into the magnet load. This enables the average incoming power from the ac line to be constant while the peak magnet power is pulsed to +/- 18 MWatts. Simulations and waveforms of this power supply will be presented.

  15. The influence of the political, economic and main force risk factors on the power system

    International Nuclear Information System (INIS)

    Barbu, C.; Ruxanda, G.

    1996-01-01

    This paper deals mainly with the economic aspects of the Romanian power development policy in the context of European Union integration. There are presented the gradual steps of regional interconnection which are currently undertaken under PHARE program. Special attention is given to the legislation, power production technology, costs, and environmental protection problems. (C.M.) 1 fig

  16. Modern technical diagnostic system for the main components of powerful turbine generator

    International Nuclear Information System (INIS)

    Ezovit, G.P.; Uglyarenko, V.P.; Burlaka, S.I.; Goroz, N.I.; Orinin, S.E.; Komaritsa, V.N.; Zav'yalov, D.N.; Mazurenko, O.A.

    2011-01-01

    The modern diagnostic system to monitor the technical state of a powerful turbine generator is considered. This system permits the detection of defects in its main components and cooling system at the early stage of their development, prevention of damage and, as a consequence, emergency shutdown of nuclear power units

  17. Quality control of three main materials for civil construction of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Feng

    2011-01-01

    The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

  18. Large screen mimic display design research for advanced main control room in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Mingguang; Yang Yanhua; Xu Jijun; Zhang Qinshun; Ning Zhonghe

    2002-01-01

    Firstly the evolution of mimic diagrams or displays used in the main control room of nuclear power plant was introduced. The active functions of mimic diagrams were analyzed on the release of operator psychological burden and pressure, the assistance of operator for the information searching, status understanding, manual actuation, correct decision making as well as the safe and reliable operation of the nuclear power plant. The importance and necessity to use the (large screen) mimic diagrams in advanced main control room of nuclear power plant, the design principle, design details and verification measures of large screen mimic display are also described

  19. Considerations for surviving the loss of a main feedwater pump at full power

    International Nuclear Information System (INIS)

    Gaydos, K.A.; Calvo, R.; Conroy, P.W.; Klein, C.M.; Mellers, J.E.

    1990-01-01

    Today's economics dictate that nuclear power operational costs be contained by addressing frequently-occurring trips that might be minimized or avoided via specific upgrades. Much recent attention has focused on the significant percentage of plant trips related to feedwater flow regulation; however, another frequent feedwater-related trip stems from the loss of a single main feedwater pump while operating at high power levels, causing a plant trip on low steam generator water-level. This paper summarizes the results of several plant-specific studies that evaluate a unit's capabilities to consistently survive the loss of a main feedwater pump from full power, and outlines a methodology for analyzing this capability

  20. Optimization of the main control room habitability system in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Guanghui; Zhao Xinyan

    2013-01-01

    This article describes the optimization of main control room habitability system in nuclear power plant. It also describes the design shortage in terms of habitability in the main control room. Through modification and optimization, habitable conditions are met for personnel staying in the emergency area of the main control room for a period of time, with an aim to take accident intervention measures smoothly and reduce the accident loss and radioactive contamination as low as possible. (authors)

  1. THE ANALYSIS OF STRUCTURAL RELIABILITY OF THE MAIN ELECTRIC CONNECTION CIRCUITS OF NUCLEAR POWER PLANTS

    Directory of Open Access Journals (Sweden)

    M. A. Korotkevich

    2017-01-01

    Full Text Available The reliability of the main circuit of electrical connections at a nuclear electric power plant that has two units with a capacity of 1,200 MW each has been determined. Reliability, economical, maneuverable properties of the atomic power plant under study are largely determined by its main circuit, so the choice of the circuit for the design and its status in the process of operation occur to be critical objectives. Main electrical connection circuits in nuclear electric power plants are selected on the basis of the schematic networks of the energy system and the land attached to the plant. The circuit of the connection of a nuclear power plant to the grid in the original normal operating modes at all stages of the construction of such a plant should provide the outcome of the full added capacity of a nuclear power plant and the preservation of its stability in the power system without the influence of the emergency system automatics when any outgoing transmission line is disabled. When selecting the main circuit the individual capacity of the installed units and their number are taken into account as well as the order of development of the plant and power supply system; the voltage on which the power of a plant is delivered; a shortcircuit current for switchgear high voltage and the need for their limitation by circuit means; the most power that can be lost when damage to any switch. A model of reliability of the main circuit of electrical connections is designed to detect all types of accidents that are possible at the coincidence of failures of elements with the repair and operational modes that differs in composition and damageability of the equipment, as well as under conditions of the development of accidents due to failure of operation of devices of relay protection and automation.

  2. IAEA activities and main achievements on human resource management and training of nuclear power plant personnel

    International Nuclear Information System (INIS)

    Kossilov, A.

    2002-01-01

    The Nuclear Power Engineering Section is responsible for implementation of the Agency's sub-programme on Engineering and Management Support for Competitive Nuclear Power. The objectives of the sub-programme is to increase Member State capabilities in utilizing the best engineering and management practices for improving NPP performance and competitiveness, optimizing plant service life and decommissioning and strengthening nuclear power infrastructure. NPES' main activities cover: Nuclear power infrastructure, Knowledge management, Personal training and qualification, Quality Management and QA, NPP life management including databases, Modern NPP control and instrumentation, and NPP performance management

  3. Prediction of the Main Engine Power of a New Container Ship at the Preliminary Design Stage

    Science.gov (United States)

    Cepowski, Tomasz

    2017-06-01

    The paper presents mathematical relationships that allow us to forecast the estimated main engine power of new container ships, based on data concerning vessels built in 2005-2015. The presented approximations allow us to estimate the engine power based on the length between perpendiculars and the number of containers the ship will carry. The approximations were developed using simple linear regression and multivariate linear regression analysis. The presented relations have practical application for estimation of container ship engine power needed in preliminary parametric design of the ship. It follows from the above that the use of multiple linear regression to predict the main engine power of a container ship brings more accurate solutions than simple linear regression.

  4. Research on cognitive reliability model for main control room considering human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Jiang Jianjun; Zhang Li; Wang Yiqun; Zhang Kun; Peng Yuyuan; Zhou Cheng

    2012-01-01

    Facing the shortcomings of the traditional cognitive factors and cognitive model, this paper presents a Bayesian networks cognitive reliability model by taking the main control room as a reference background and human factors as the key points. The model mainly analyzes the cognitive reliability affected by the human factors, and for the cognitive node and influence factors corresponding to cognitive node, a series of methods and function formulas to compute the node cognitive reliability is proposed. The model and corresponding methods can be applied to the evaluation of cognitive process for the nuclear power plant operators and have a certain significance for the prevention of safety accidents in nuclear power plants. (authors)

  5. Status of the maintenance for the KEK 12GEV-PS main ring and power supply

    International Nuclear Information System (INIS)

    Sato, Hikaru; Igarashi, Susumu; Marutsuka, Katsumi; Mikawa, Katsuhiko; Shirakata, Masashi; Sueno, Tsuyoshi; Tokuda, Noboru

    2004-01-01

    More than 30 years passed since the KEK 12GeV-PS construction, some of accelerator equipments are highly radiated, especially the injection and the extraction equipments. In recent years, the higher intensity beam has been required for such as the long baseline neutrino oscillation experiment and rare decay experiments. Then, the circumference of the maintenance work has become severe. Further, almost equipments of main ring and power supply have deteriorated. Status of the Maintenance for the KEK 12GeV-PS main ring and power supply are presented. (author)

  6. Simulation of the control system for the KEK main ring power supply-II

    International Nuclear Information System (INIS)

    Kabe, Atsushi; Sato, Hikaru; Masuda, Masayoshi; Takeda, Masahiro; Nakano, Michio

    1977-05-01

    The tracking error between the magnetic field of the bending magnets and that of the quadrupole magnets is a very important problem of the KEK main ring power supply. Tacking performance is simulated using DDS (Digital Dynamics Simulator) in cases of 8 GeV and 12 GeV operation of the KEK main ring. The results of simulation coincide with the data of actual system. (auth.)

  7. The MISO Wiretap Channel with Noisy Main Channel Estimation in the High Power Regime

    KAUST Repository

    Rezki, Zouheir

    2017-02-07

    We improve upon our previous upper bound on the secrecy capacity of the wiretap channel with multiple transmit antennas and single-antenna receivers, with noisy main channel state information (CSI) at the transmitter (CSI-T). Specifically, we show that if the main CSI error does not scale with the power budget at the transmitter P̅, then the secrecy capacity is )bounded above essentially by log log (P̅ yielding a secure degree of freedom (sdof) equal to zero. However, if the main CSI error scales as O(P̅-β), for β ∈ [0,1], then the sdof is equal to β.

  8. The MISO Wiretap Channel with Noisy Main Channel Estimation in the High Power Regime

    KAUST Repository

    Rezki, Zouheir; Chaaban, Anas; Alomair, Basel; Alouini, Mohamed-Slim

    2017-01-01

    We improve upon our previous upper bound on the secrecy capacity of the wiretap channel with multiple transmit antennas and single-antenna receivers, with noisy main channel state information (CSI) at the transmitter (CSI-T). Specifically, we show that if the main CSI error does not scale with the power budget at the transmitter P̅, then the secrecy capacity is )bounded above essentially by log log (P̅ yielding a secure degree of freedom (sdof) equal to zero. However, if the main CSI error scales as O(P̅-β), for β ∈ [0,1], then the sdof is equal to β.

  9. Power law of distribution of emergency situations on main gas pipeline

    Science.gov (United States)

    Voronin, K. S.; Akulov, K. A.

    2018-05-01

    The article presents the results of the analysis of emergency situations on a main gas pipeline. A power law of distribution of emergency situations is revealed. The possibility of conducting further scientific research to ensure the predictability of emergency situations on pipelines is justified.

  10. High resolution ADC interface to main magnet power supply at the NSLS

    Energy Technology Data Exchange (ETDEWEB)

    Bordoley, M.

    1993-07-01

    Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device`s AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller.

  11. High resolution ADC interface to main magnet power supply at the NSLS

    Energy Technology Data Exchange (ETDEWEB)

    Bordoley, M.

    1993-01-01

    Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device's AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller.

  12. High resolution ADC interface to main magnet power supply at the NSLS

    International Nuclear Information System (INIS)

    Bordoley, M.

    1993-01-01

    Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device's AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller

  13. Main Power Distribution Unit for the Jupiter Icy Moons Orbiter (JIMO)

    Science.gov (United States)

    Papa, Melissa R.

    2004-01-01

    Around the year 2011, the Jupiter Icy Moons Orbiter (JIMO) will be launched and on its way to orbit three of Jupiter s planet-sized moons. The mission goals for the JIMO project revolve heavily around gathering scientific data concerning ingredients we, as humans, consider essential: water, energy and necessary chemical elements. The JIM0 is an ambitious mission which will implore propulsion from an ION thruster powered by a nuclear fission reactor. Glenn Research Center is responsible for the development of the dynamic power conversion, power management and distribution, heat rejection and ION thrusters. The first test phase for the JIM0 program concerns the High Power AC Power Management and Distribution (PMAD) Test Bed. The goal of this testing is to support electrical performance verification of the power systems. The test bed will incorporate a 2kW Brayton Rotating Unit (BRU) to simulate the nuclear reactor as well as two ION thrusters. The first module of the PMAD Test Bed to be designed is the Main Power Distribution Unit (MPDU) which relays the power input to the various propulsion systems and scientific instruments. The MPDU involves circuitry design as well as mechanical design to determine the placement of the components. The MPDU consists of fourteen relays of four different variations used to convert the input power into the appropriate power output. The three phase system uses 400 Vo1ts(sub L-L) rms at 1000 Hertz. The power is relayed through the circuit and distributed to the scientific instruments, the ION thrusters and other controlled systems. The mechanical design requires the components to be positioned for easy electrical wiring as well as allowing adequate room for the main buss bars, individual circuit boards connected to each component and power supplies. To accomplish creating a suitable design, AutoCAD was used as a drafting tool. By showing a visual layout of the components, it is easy to see where there is extra room or where the

  14. Audible Noise Measurement and Analysis of the Main Power Apparatus in UHV GIS Substations

    Directory of Open Access Journals (Sweden)

    Zhou Nian Guang

    2016-01-01

    Full Text Available Investigation of audible noise characteristics of the main power apparatus in UHV GIS substations provides essential statistics for the noise prediction and control. Noise pressure level, spectrum and attenuation characteristics of the main transformers and high voltage (HV reactors are measured and analyzed in this paper. The result shows that the main transformer and HV reactor have identical A-weighted equivalent sound pressure level. The medium- and low-frequency noises are the primary components in the spectral. More attention should be paid to the low-frequency bands in the noise control process. The noise of cooling fan has a large influence on that of the main transformer. Without the consideration of corona noise, the average A-weighted sound pressure level shows an overall decreasing trend with the increase of the propagation distance. Obvious interference phenomenon of the noises at 100 and 200Hz exists in the noise propagation process.

  15. The main features of control and operation of steam turbines at nuclear power plants

    International Nuclear Information System (INIS)

    Czinkoczky, B.

    1981-01-01

    The output and speed control of steam turbines at nuclear power plants as well as the combination of both controls are reviewed and evaluated. At the same time the tasks of unit control at nuclear power plants, the control of steady main steam pressure and medium pressure of primary circuit, further the connection of reactor and turbine controls and the self-controlling properties of pressurized water reactor are dealt with. Hydraulic and electro-hydraulic speed control, the connection of cach-up dampers and speed control and the application of electro-hydraulic signal converters are discussed. The accomplishment of protection is also described. (author)

  16. A comprehensive search for “anomalies” from neutrino and anti-neutrino oscillations at large mass differences (Δm^2 ~ 1eV^2) with two LAr–TPC imaging detectors at different distances from the CERN-PS.

    CERN Document Server

    Rubbia, C; Bagliani, D; Baibussinov, B; Bilokon, H; Boffelli, F; Bonesini, M; Calligarich, E; Canci, N; Centro, S; Cesana, A; Cieslik, K; Cline, D B; Cocco, A G; De Gerone, M; Dequal, D; Dermenev, A; Dolfini, R; Dussoni, S; Farnese, C; Fava, A; Ferrari, A; Fiorillo, G; Garvey, G T; Gatti, F; Gibin, D; Gigli Berzolari, A; Gninenko, S; Guber, F; Guglielmi, A; Haranczyk, M; Holeczek, J; Ivashkin, A; Kirsanov, M; Kisiel, J; Kochanek, I; Kurepin, A; Łagoda, J; Louis, W C; Lucchini, G; Mania, S; Mannocchi, G; Matveev, V; Menegolli, A; Meng, G; Mills, G B; Montanari, C; Otwinowski, S; Palczewski, T J; Perfetto, F; Periale, L; Picchi, P; Pietropaolo, F; Płoński, P; Rappoldi, A; Raselli, G L; Rossella, M; Sala, P; Scantamburlo, E; Scaramelli, A; Segreto, E; Sergiampietri, F; Suvorova, O; Stefan, D; Stepaniak, J; Sulej, R; Terrani, M; Testera, G; Tlisov, D; Trinchero, G; Van de Water, R G; Varanini, F; Ventura, S; Vignoli, C; Wang, H G; Yang, X; Zani, A; Zaremba, K

    2011-01-01

    The present proposal describes an experimental search of sterile neutrinos beyond the Standard Model with the CERN-PS beam and the innovative technology of imaging in ultra-pure cryogenic liquid Argon. The proposal is based on two strictly identical LAr-TPC detectors observing the electron-neutrino signal in the ”Far” and “Near” positions, the first one of about 600 tons placed 850 m the second one of about 150 tons at about 6.5 times shorter distance from the proton target. This project will exploit the ICARUS T600 — now running in the underground experiment CNGS2 with neutrinos from the CERN-SPS — moved from GranSasso to the CERN “Far” position. The additional T150 will be constructed and located in the “Near” position. In the two positions, the radial and energy spectra of the nu_e beam are practically identical. Comparing the two detectors, in absence of oscillations, all cross sections and experimental biases cancel out and the two experimentally observed event distributions must be ...

  17. Policy planning for nuclear power: an overview of the main issues and requirements

    International Nuclear Information System (INIS)

    1995-05-01

    The report contains information on the political, governmental, economic, financial and technical issues and requirements associated with planning and implementing a safe, economic and reliable nuclear power programme. It highlights the main areas in which policies must be developed and decisions taken, as well as the role and responsibilities of government, the plant owner and national industry. Also presented are the main criteria to assist policy planners in defining options and strategies which can achieve a balance among such objectives as cost effective and efficient electricity production, realistic and acceptable financing arrangements, national development requirements, safety and environmental protection. (NHA)

  18. Validation study on reliability analysis of main safety system in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Nam Jin; Cho, Chang Keun; Kim, Yong Hui; Kim, Tae Hyeong; Hong, Seo Kee; Park, Keon Woo; Park, Chang Jea [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Cheong, Woo Sik [Institute for Advanced Engineering, Yongin (Korea, Republic of); Park, Moon Kyu [KEPRI, Taejon (Korea, Republic of)

    1993-12-15

    The scope and contents of this validation study are to review the design changes of the four main safety systems in Wolsong 2/3/4 Nuclear Power Plants, to review the consideration of the above design changes in the AECL reports, the structure of fault trees, and the data base used in the quantification of the fault trees, to quantify the unavailabilities of main safety systems and check them if they meet the requirements, and to recommend desirable design changes in the emergency core cooling system to reduce the unavailability.

  19. In-service diagnostics of main circulating circuit pipes of WWER nuclear power plants

    International Nuclear Information System (INIS)

    Svoboda, V.; Merta, J.; Merta, V.

    1982-01-01

    The application is discussed of the acoustic emission method for testing the integrity of the components of the main circulating circuit of the WWER 440 nuclear power plant. A description is given of the main circulating circuit and a stress analysis on the basis of strength computations considering operating modes is presented. An analysis is also presented of the possible damage of the pipe material as related to the application of the acoustic emission method for in-service inspection of the pipes. Certain practical problems of application are discussed. (author)

  20. Flexibility analysis of main primary heat transport system : Narora Atomic Power Project

    International Nuclear Information System (INIS)

    Rastogi, S.K.

    1975-01-01

    The paper presents flexibility analysis problem of main primary heat transport system and the approximate analysis that has been made to estimate the loads coming on major equipments. The primary heat transport system for Narora Atomic Power Project is adopting vertical steam generators and pumps equally divided on either side of the reactor with inter-connecting pipes and feeders. Since the system is mainly spring supported with movement of a few points in certain direction defined but no anchorage, it represents a good problem for flexibility analysis which can only be solved in one step by developing a good computer programme. (author)

  1. Digitized operator evaluation system for main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Chen Yu; Yan Shengyuan; Chen Wenlong

    2014-01-01

    In order to evaluate the human-machine system matching relation of main control room in nuclear power plant accurately and efficiently, the expression and parameters of operator human body model were analyzed, and the evaluation required function of digital operator was determined. Based on the secondary development technology, the digital operator evaluation body model was developed. It could choose generation, gender, operation posture, single/eyes horizon, and left/right hand up to the domain according to the needs of specific evaluation, it was used to evaluate whether display information can be visible and equipment can be touch, and it also has key evaluation functions such as workspace and character visibility at the same time. The examples show that this method can complete the evaluation work of human-machine matching relation for main control room of nuclear power plant accurately, efficiently and quickly, and achieve the most optimal human-machine coordination relationship. (authors)

  2. The New Control and Interlock System for the SPS Main Power Converters

    CERN Document Server

    Denis, B; Mugnier, C; Varas, J

    1999-01-01

    The Control and Interlock System (CIS) of the SPS main power converters was designed in the mid-70s and became increasingly difficult to maintain. A new system based on Programmable Logic Controllers has been developed by an external contractor in close collaboration with CERN. The system is now operational and fully integrated in the SPS/LEP control infrastructure. The CIS is the first major contracted industrial solution used to control accelerator equipment directly involved in the production of particle beams at CERN. This paper gives an overview of the SPS main power converter installation and describes both the contractual and technical solution adopted for the CIS. It first explains how the system was specified and how the contractual relationship was defined to respect CERN’s purchasing rules and the operational requirements of the SPS accelerator. The architectural design of the new system is presented with special emphasis on how the conflict between safety and availability has been addressed.

  3. The main steps of the Romanian nuclear power program development - Accumulated experience

    International Nuclear Information System (INIS)

    Chirica, T.; Popescu, D.; Condu, M.; Vatamanu, M.

    1998-01-01

    The paper presents a historical summary of the Romanian Nuclear Power Program development, providing details for the main criteria and principles the Program was based upon, the contracts signed with the foreign partners to implement it, and the national participation (site contractors, suppliers and design organizations). The effect of the equipment assimilation program on the NPP Cernavoda (5x700 MWe) and especially on Unit 1 schedule and performance is analyzed. Further on the impact of the transition from centralized to a market economy over the Romanian Nuclear Power Program development is analyzed, providing information's on its actual status and perspectives for the next 20 years. A description of the NPP Cernavoda Unit 1 actual progress and of the main steps performed by RENEL to get finance to complete NPP Cernavoda Unit 2 is included. Finally there is summarized the accumulated experience, and its feed back on RENEL strategy to complete NPP Cernavoda Unit 2. (author)

  4. Re-Examining first principles of regulation: NRG power marketing, LLC v. Maine public utilities Commission

    Energy Technology Data Exchange (ETDEWEB)

    Haskell, Mark R.

    2010-03-15

    Maine PUC and Morgan Stanley have resolved some of the key issues facing the energy industry. The Supreme Court has plainly and directly in both cases reaffirmed the central role that private contracts play in the energy industry and set terms to balance the need to secure long-term investment with the public interest that lies at the heart of the Federal Power Act. (author)

  5. Main lessons based on the Chernobyl nuclear power plant accident liquidation experience

    International Nuclear Information System (INIS)

    Vasil'chenko, V.N.; Nosovskij, A.V.

    2006-01-01

    The authors review the main lessons of the Chernobyl nuclear power plant accident and the liquidation of its consequences in the area of the nuclear reactors safety operation, any major accident management, liquidation accident consequences criteria, emergency procedures, preventative measures and treatment irradiated victims, the monitoring methods etc. The special emphasis is put on the questions of the emergency response and the antiaccidental measures planning in frame of international cooperation program

  6. The active filter voltage ripple correction system of the Brookhaven AGS main magnet power supply

    International Nuclear Information System (INIS)

    Marneris, I.; Bonati, R.; Geller, J.; Sandberg, J.N.; Soukas, A.

    1995-01-01

    This paper, and a companion paper, describe the improvements to the Main Magnet Power Supply (MMPS) so that it enables a more flexible operation of the AGS, enhances its reliability, and also improves the MMPS's ultimate performance specifications. One of the major areas for the latter is the fixed target program operating off the AGS slow extracted beam lines. The active filter, by improving the MMPS output ripple, is instrumental in the improvement of the ultimate duty factor of the extraction beam spill

  7. Seismic margin review of the Maine Yankee Atomic Power Station: Fragility analysis

    International Nuclear Information System (INIS)

    Ravindra, M.K.; Hardy, G.S.; Hashimoto, P.S.; Griffin, M.J.

    1987-03-01

    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants

  8. OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring

    2012-10-01

    This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

  9. Seismic margin review of the Maine Yankee Atomic Power Station: Fragility analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ravindra, M. K.; Hardy, G. S.; Hashimoto, P. S.; Griffin, M. J.

    1987-03-01

    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants.

  10. Policy planning for nuclear power: An overview of the main issues and requirements

    International Nuclear Information System (INIS)

    1993-08-01

    This special report, Policy Planning for Nuclear Power: An Overview of the Main Issues and Requirements, has been prepared in response to the express request of a number of IAEA Member States for a document to assist makers in developing countries on the introduction of nuclear power. The report contains information on the political, governmental, economic, financial and technical issues and requirements associated with planning and implementing a safe, economic and reliable nuclear power programme. It highlights the main areas in which policies must be developed and decisions taken, as well as the role and responsibilities of government, the plant owner and national industry. Also presented are the main criteria to assist policy planners in defining options and strategies which can achieve a balance among such objectives as cost effective and efficient electricity production, realistic and acceptable financing arrangements, national development requirements, safety and environmental protection. Further information and details on the technical and other issues presented in this report are given in the list of related IAEA publications and documents at the end of this report

  11. Derivation of main drivers affecting the possibility of human errors during low power and shutdown operation

    International Nuclear Information System (INIS)

    Kim, Ar Ryum; Seong, Poong Hyun; Park, Jin Kyun; Kim, Jae Whan

    2016-01-01

    In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers which are commonly called as performance shaping factors (PSFs) are aspects of the human's individual characteristics, environment, organization, or task that specifically decrements or improves human performance, thus respectively increasing or decreasing the likelihood of human errors. In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers which

  12. Derivation of main drivers affecting the possibility of human errors during low power and shutdown operation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ar Ryum; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of); Park, Jin Kyun; Kim, Jae Whan [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers which are commonly called as performance shaping factors (PSFs) are aspects of the human's individual characteristics, environment, organization, or task that specifically decrements or improves human performance, thus respectively increasing or decreasing the likelihood of human errors. In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers

  13. High-inertia hermetically sealed main coolant pump for next generation passive nuclear power plants

    International Nuclear Information System (INIS)

    Kujawski, Joseph M.; Nair, Bala R.; Vijuk, Ronald P.

    2003-01-01

    The main coolant pump for the Westinghouse AP1000 advanced passive nuclear power plant represents a significant scale-up in power, flow capacity, and physical size from its predecessor designed for the smaller AP600 power plant. More importantly, the AP1000 pump incorporates several innovative features that contribute to improved efficiency, operational reliability, and plant safety. The features include an internals design which provides the highest hydraulic efficiency achieved in commercial nuclear power plant applications. Another feature is the use of a distributed inertial mass system in the rotating assembly to develop the high rotational inertia to meet the extended system flow coastdown requirement for core heat removal in the event of loss of power to the pumps. This advanced canned motor pump also incorporates the latest development in higher operating voltage, providing plant designers with the ability to eliminate plant transformers and operate directly on the site electrical bus in many cases. The salient features of the pump design and performance data are presented in this paper. (author)

  14. Ripple characteristic of the main ring magnet power supply for the KEK 12 GeV PS

    International Nuclear Information System (INIS)

    Sato, Hikaru; Sueno, Tuyosi; Mikawa, Katsuhiko

    1995-01-01

    First of all, general description of the main ring magnet power supply for the KEK 12 GeV PS will be described. The main power supply consists of thyristor rectifiers, DC filters, reactive power compensators, AC harmonic filters and control systems. Devices and control systems for suppressing ripple component of magnet field will be described. (author)

  15. Study of 1 MW neutron source synchrotron dual frequency power circuit for the main ring magnets

    International Nuclear Information System (INIS)

    McGhee, D.G.

    1993-01-01

    This paper describes the proposed design of the resonant power circuits for the 1-MW neutron source synchrotron's main ring magnets. The synchrotron is to have a duty cycle of 30 Hz with a maximum upper limit of operation corresponding to 2.0 GeV and a maximum design value of 2.2 GeV. A stability of 30 ppM is the design goal for the main bending and focusing magnets (dipoles and quadruples), in order to achieve an overall stabffity of 100 ppm when random field and position errors of the magnets are included. The power circuits of this design are similar to those used in Argonne's Intense Pulsed Neutron Source (IPNS) where the energy losses during each cycle are supplied by continuous excitation from modulated multiphase DC power supplies. Since only 50% of the 30-Hz sinewave is used for acceleration, a dual-frequency resonant magnet circuit is used in this design. The 30-Hz repetition rate is maintained with a 20-Hz magnet guide field during acceleration and a 60-Hz reset field when no beam is present. This lengthens the guide-field rise time and shortens the fall time, improving the duty factor for acceleration. The maximum B dot is reduced by 33% during acceleration and hence, the maximum rf voltage/turn is reduced by 56%

  16. A proposal to pulse the Bevatron/Bevalac main guide field magnet with SCR power supplies

    International Nuclear Information System (INIS)

    Frias, B.; Alonso, J.; Dwinell, R.; Lothrop, F.

    1989-01-01

    The Bevatron/Bevalac Main Guide Field Power Supply was originally designed to provide a 15,250 Volt DC. at sign 8400 Ampere peak magnet pulse. Protons were accelerated to 6.2 Gev. The 128 Megawatt (MW) pulse required two large motor-generator (MG) sets with 67 ton flywheels to store 680 Megajoules of energy. Ignitron rectifiers are used to rectify the generator outputs. Acceleration of heavy ions results in an operating schedule with a broad range of peak fields. The maximum field of 12.5 kilogauss requires a peak pulse of 80 MW. Acceleration of ions to 1.0 kilogauss requires an 8 MW peak pulse. One MG set can provide pulses below 45 MW. Peak pulses of less than 15 MW are now a large block of the operating schedule. A proposal has been made to replace the existing MG system with eight SCR power supplies for low field operation. The SCR supplies will be powered directly from the Lawrence Berkeley Laboratory's 12.3 KV. power distribution system. This paper describes the many advantages of the plan. 4 refs., 3 figs., 3 tabs

  17. Study on quality control measures of static casting main pipe in PWR nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Zhenbiao; Li Guanying; Liu Zhicheng

    2013-01-01

    This study analyzes the main reasons which impact the quality of primary pipe static casting elbows in PWR-M310 nuclear power plant. The quality control measures are developed from the election and inspection of material, improving sand production and casting process, improving lean management of personnel. The static casting defects of primary pipe elbows for Fuqing Unit 1 and 2 were down to less than 50% of the former project. The quality of static casting for the primary pipe elbows was significantly improved. Moreover, the implementation saves human resources and financing to repair casting defects, and also helps to win the delivery schedule. The quality control measures are good reference for improving primary pipe casting process. This study provides valuable experience for further study of improving the quality of static casting for the primary pipe of PWR nuclear power plant. (authors)

  18. Main Characteristics of Nuclear Power Plants in the European Union and Candidate Countries

    International Nuclear Information System (INIS)

    Lillington, J.N.; Turland, B.D.; Haste, T.J.; Seiler, J.M.; Tapia, J.; Carretero, A.; Perez, T.; Geutges, A.; Sehgal, B.R.; Mattila, L.; Holmstrom, H.; Karwat, H.; Maroti, L.; Husarcek, J.

    2001-10-01

    The main objective was to advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonization of safety requirements and practices in an enlarged European Union Part of this activity was to provide a summary of the plant characteristics of the operating civil nuclear power plants in the EU Member and Candidate Countries. The present report provides these data in three formats: A reference table which lists the main characteristics of nuclear power-producing reactors operating in the European Union (EU) and Candidate Countries, as at 31 December 1999. Also included, for the sake of completeness, are data for reactors in the former Soviet Union, such as Russia and the Ukraine. The format adopted follows that in the annual International Atomic Energy Agency (IAEA) reference data report ''Nuclear Power Reactors of the World'', from which much of the information was taken; A summary table indicating totals by reactor type covering Western and Eastern Europe separately, again from IAEA sources, giving number of plant, total generating capacity and total years in operation. A list of the abbreviations for different reactor types is also provided; A set of detailed data sheets giving main plant characteristics for different reactor types ordered by country. These data sheets cover reactors in EU Member and Candidate Countries only. Details are provided on the origin of the data where these are available, so that further information may be obtained if desired and where permitted by commercial and/or proprietary considerations. (author)

  19. Service life monitoring of the main components at the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Hahn, J.; Vincour, D.

    2007-01-01

    Knowledge and experience gained from the introduction and periodical implementation of life assessment of the major components of the Temelin nuclear power plant is summarized. The initial Soviet technical design of the plant did not incorporate lifetime monitoring and evaluation, therefore it was completed with demonstrative strength and lifetime calculations from Czech companies. Moreover, a Westinghouse primary circuit diagnosis and monitoring system, including the monitoring of temperature and pressure cycles for low-cycle fatigue evaluation, was installed at the plant. The DIALIFE code for the calculation of mainly the low-cycle fatigue of the key pressure components, was developed and installed subsequently as a superstructure to the monitoring system. (author)

  20. Plug the socket of the main closing valve in a nuclear power plant

    International Nuclear Information System (INIS)

    Neupauer, J.; Bednar, B.

    1988-01-01

    The plug is designed for closing the main closing valve socket during a refuelling shutdown of a nuclear power plant. The plug is fixed in the using jaws forced against the socket ring part. The socket is sealed by expanding a ring between two cone trays. A valve provided in the plug allows draining the pipe. The plug is inserted in the socket using a jib suspended on a rail. Following sealing both sockets the inner surfaces of the closing valve can be decontaminated. Following decontamination, a water-proof cover is slid over the plug protecting the plug moving mechanism from damage. (J.B.). 1 fig

  1. Performance Evaluation and Quality Assurance Management during the Series Power Tests of LHC Main Lattice Magnets

    CERN Document Server

    Siemko, A

    2008-01-01

    Within the LHC magnet program a series production of superconducting dipoles and quadrupoles has recently been completed in industry and all magnets were cold tested at CERN. The main features of these magnets are: two-in-one structure, 56 mm aperture, two layer coils wound from 15.1 mm wide Nb-Ti cables, and all-polyimide insulation. This paper reviews the process of the power test quality assurance and performance evaluation, which was applied during the LHC magnet series tests. The main test results of magnets tested in both supercritical and superfluid helium, including the quench training, the conductor performance, the magnet protection efficiency and the electrical integrity are presented and discussed in terms of the design parameters and the requirements of the LHC project.

  2. Thermal expansion measurement of turbine and main steam piping by using strain gages in power plants

    International Nuclear Information System (INIS)

    Na, Sang Soo; Chung, Jae Won; Bong, Suk Kun; Jun, Dong Ki; Kim, Yun Suk

    2000-01-01

    One of the domestic co-generation plants have undergone excessive vibration problems of turbine attributed to external force for years. The root cause of turbine vibration may be shaft alignment problem which sometimes is changed by thermal expansion and external force, even if turbine technicians perfectly performed it. To evaluate the alignment condition from plant start-up to full load, a strain measurement of turbine and main steam piping subjected to thermal loading is monitored by using strain gages. The strain gages are bonded on both bearing housing adjusting bolts and pipe stoppers which installed in the x-direction of left-side main steam piping near the turbine inlet in order to monitor closely the effect of turbine under thermal deformation of turbine casing and main steam piping during plant full load. Also in situ load of constant support hangers in main steam piping system is measured by strain gages and its results are used to rebalance the hanger rod load. Consequently, the experimental stress analysis by using strain gages turns out to be very useful tool to diagnose the trouble and failures of not only to stationary components but to rotating machinery in power plants

  3. Main characteristics of the radioactive enrichment in ashes produced in coal-fired power stations

    International Nuclear Information System (INIS)

    Baeza, Antonio; Corbacho, Jose A.; Cancio, David; Robles, Beatriz; Mora, Juan C.

    2008-01-01

    Under contract with the Spain's 'Nuclear Safety Council', a study is being conducted of the nation's largest nominal output coal-fired power stations. Its purpose is to assess the radiological impact on workers and local populations due to this source of NORM activity. One of the aspects of particular interest is the study of the radioactive enrichment in the combustion wastes relative to the different coals used as fuel (usually local bituminous coal or lignite, or imported coal). These wastes consist of fly ash (mostly fine particles collected in electrostatic precipitators), and bottom ash (larger in size, and collected wet or dry in hoppers below the boilers). In general terms, the enrichment factors measured were between 2 and 18 for the radionuclides 40 K, 226 Ra, 232 Th, and 210 Po. The magnitude of this enrichment factor depended mainly on the ash content of each coal, and hence on the type of coal used as fuel and the specific operation cycle in the different power stations. For the radionuclides 40 K, 226 Ra, and 232 Th, the enrichment was relatively similar in value in the fly and bottom ashes produced by the different types of coal used in the power stations studied. For 210 Po, however, as was expected, the enrichment was much greater in the fly ash than in the bottom ash for each coal analyzed. (author)

  4. Factors analysis of water hammer in FLOWMASTER for main feedwater systems of PWR nuclear power plants

    International Nuclear Information System (INIS)

    Wang Xin; Han Weishi

    2010-01-01

    The main feedwater system of a nuclear power plant (NPP) is an important part in ensuring the cooling of a steam generator. It is the main pipe section where water hammers frequently occur. Studying the regulator patterns of water hammers in the main feedwater systems is significant to the stable operation of the system. This article focuses on a parametric study to avoid the consequences of water hammer effect in PWR by employing a general purpose fluid dynamic simulation software-FLOWMASTER. Through FLOWMASTER's transient calculating functions, a mathematical model is established with boundary conditions such as feedwater pumps, control valves, etc., calculations of water hammer pressure when feedwater pumps and control valves shut down, and simulations during instantaneous changes in water hammer pressure. Combining a plethora of engineering practical examples, this research verified the viability of calculating water hammer pressure through FLOWMASTER's transient functions and we found out that, increasing the periods of closure of control valves and feedwater pumps control water hammers effectively. We also found out that changing the intervals of closing signals to feedwater pumps and control valves aid to relieve hydraulic impact. This could be a guideline for practical engineering design and system optimization. (author)

  5. Water hammer calculation and analysis in main feedwater system of PWR nuclear power plants

    International Nuclear Information System (INIS)

    Wang Xin; Han Weishi

    2010-01-01

    The main feedwater system of a nuclear power plant is an important part in ensuring the cooling of the steam generator. Moreover, it is the main pipe section where water hammers frequently occur. Studying the regular patterns of water hammers to the main feedwater system is significant to the stable operation of the system. The paper focuses on the study of water hammers through Flowmaster's transient calculating function to establish a mathematical model with boundary conditions such as a feedwater pump, control valves, etc.; calculation of the water hammers pressure when feedwater pumps and control valves shut down; exporting the instantaneous change in solution of pressure. Combined with engineering practical examples, the conclusions verify the viability of calculating the water hammers pressure through Flowmaster's transient function, increasing the periods of closure of control valves and feedwater pumps control water hammers effectively, changing the intervals of closing signals to feedwater pumps and control valves to relieve hydraulic impact. This could be a guideline for practical engineering design and system optimization. (authors)

  6. Fault diagnosis of main coolant pump in the nuclear power station based on the principal component analysis

    International Nuclear Information System (INIS)

    Feng Junting; Xu Mi; Wang Guizeng

    2003-01-01

    The fault diagnosis method based on principal component analysis is studied. The fault character direction storeroom of fifteen parameters abnormity is built in the simulation for the main coolant pump of nuclear power station. The measuring data are analyzed, and the results show that it is feasible for the fault diagnosis system of main coolant pump in the nuclear power station

  7. Establishment of land model at the Shika Nuclear Power Plant. Mainly, on rock board classification

    International Nuclear Information System (INIS)

    Katagawa, Hideki; Hashimoto, Toru; Hirano, Shuji

    1999-01-01

    In order to grasp engineering properties of basic land of constructions, there is rock board classification as a method to classify whole of rock board to some groups considerable to be nearly equal on its properties. Among the method, various methods in response to its aim and characteristics are devised, and for a classification to hard rock board, the Denken type rock board classification considering degree of weathering to its main element and so forth are well known. The basic rock board of the Shika Nuclear Power Plant is composed of middle and hard types of rock, and its weathering is limited to its shallow portion, most of which are held at fresh condition. For such land, a new classification standard in response to characteristics of land was established. Here were introduced on a progress to establish a new classification standard, its application results and rock board properties. (G.K.)

  8. Main phases of siting for nuclear power plants with review of required investigations

    International Nuclear Information System (INIS)

    Malbasa, N.

    1984-01-01

    The purpose of the article is a short description of the main phases in the process of siting for nuclear power plants as interpreted and applied by the Institut za elektroprivredu, Zagreb in the screening, comparison and evaluation of the sites for NPPs in the SR of Croatia. The scope and purpose, as well as review of required data and investigations for each particular phase are given. Common used methods for the comparison of sites are described and example of rejection criteria applicable for early phases of the siting is proposed. It is given a list of the most important activities which detailed analysis id indispensable for ending of the evaluation and getting a site permit from the regulatory body. A legal and regulatory basis for carrying out the siting process is also described. (author)

  9. Feasibility study for biomass power plants in Thailand. Volume 1. Main report. Export trade information

    International Nuclear Information System (INIS)

    1997-01-01

    This study, conducted by Black and Veatch, was funded by the U.S. Trade and Development Agency. The report presents a technical and commercial analysis for the development of three nearly identical electricity generating facilities (biomass steam power plants) in the towns of Chachoengsao, Suphan Buri, and Pichit in Thailand. The Main Report is divided into the following sections: (1.0) Executive Study; (2.0) Project Objectives; (3.0) Review of Combustion Technology for Biomass Fueled Steam Generator Units; (4.0) Conceptual Design; (5.0) Plant Descriptions; (6.0) Plant Operations Staffing; (7.0) Project Schedule; (8.0) Project Cost Estimate; (9.0) Financial Analysis; Appendix - Financial Analysis

  10. VME Switch for CERN's PS Analog Video System

    CERN Document Server

    Acebes, I; Heinze, W; Lewis, J; Serrano, J

    2003-01-01

    Analog video signal switching is used in CERN's Proton Synchrotron (PS) complex to route the video signals coming from Beam Diagnostics systems to the Meyrin Control Room (MCR). Traditionally, this has been done with custom electromechanical relay-based cards controlled serially via CAMAC crates. In order to improve the robustness and maintainability of the system, while keeping it analog to preserve the low latency, a VME card based on Analog Devices' AD8116 analog matrix chip has been developed. Video signals go into the front panel and exit the switch through the P2 connector of the VME backplane. The module is a 16 input, 32 output matrix. Larger matrices can be built using more modules and bussing their outputs together, thanks to the high impedance feature of the AD8116. Another VME module takes the selected signals from the P2 connector and performs automatic gain to send them at nominal output level through its front panel. This paper discusses both designs and presents experimental test results.

  11. Beam Quality Preservation in the CERN PS-SPS Complex

    CERN Multimedia

    Arduini, Gianluigi

    2004-01-01

    The LHC will require beams of unprecedented transverse and longitudinal brightness. Their production imposes tight constraints on the emittance growth in each element of the LHC injector chain, namely the PS-SPS Accelerator Complex. The problems encountered at the different stages of the acceleration in the complex span a wide range of topics, such as injection matching, RF gymnastics, space charge, transverse and longitudinal single- and coupled-bunch instabilities, and electron cloud effects. The measurement techniques developed and applied to identify and study the various sources of emittance dilution to the high precision required for the LHC beams and the solutions found to control such phenomena are illustrated.

  12. The CERN PS/SL Controls Java Application Programming Interface

    International Nuclear Information System (INIS)

    I. Deloose; J. Cuperus; P. Charrue; F. DiMaio; K. Kostro; M. Vanden Eynden; W. Watson

    1999-01-01

    The PS/SL Convergence Project was launched in March 1998. Its objective is to deliver a common control as infrastructure for the CERN accelerators by year 2001. In the framework of this convergence activity, a project was launched to develop a Java Application Programming Interface (API) between programs written in the Java language and the PS and SL accelerator equipment. This Java API was specified and developed in collaboration with TJNAF. It is based on the Java CDEV [1] package that has been extended in order to end up with a CERN/TJNAF common product. It implements a detailed model composed of devices organized in named classes that provide a property-based interface. It supports data subscription and introspection facilities. The device model is presented and the capabilities of the API are described with syntax examples. The software architecture is also described

  13. The (7,7) optics at CERN PS

    CERN Document Server

    Serluca, M; Efthymiopoulos, I; Sperati, F; Sterbini, G; Tecker, F; Zisopoulos, P

    2017-01-01

    The PS lattice is composed by one hundred combinedfunction magnets, which set the bare tune of the machineto (Qh,Qv) = (6.25, 6.28). Low energy quadrupoles areused at injection to move the tune in a limited working pointarea. In particular the vertical tune is moved below 6.25 toavoid the structural resonance 8Qv= 50 coupled with spacecharge, which leads to strong losses. In view of the highdemands in terms of beam brightness for LIU and HL-LHCprojects, the interest of exploring different integer tune work-ing area started during last years. During 2016, for the firsttime, it has been possible to explore the (7,7) tune workingarea at injection using the auxiliary circuits of the combinedfunction magnets. A finite-element magnetic model, underdevelopment, has been used to predict the required currentsin order to get the desired optical parameters. In this pa-per we present the results and issues encountered duringthe Machine Development (MD) studies about the injectionin the (7,7) area along with optics and be...

  14. Study of an energy upgrade of the CERN PS Booster

    CERN Document Server

    Hanke, K; Angoletta, M E; Bartmann, W; Bartolome, S; Bertone, C; Blas, A; Borburgh, J; Bozzini, D; Butterworth, A; Carli, C; Dahlen, P; Dobers, T; Findlay, A; Folch, R; Gilbert, N; Hansen, J; Hermanns, T; Jensen, S; Le Roux, P; Lopez-Hernandez, L A; Mahner, E; Masi, A; Mikulec, B; Muttoni, Y; Newborough, A; Nisbet, D; Nonis, M; Olek, S; Paoluzzi, M; Pittet, S; Puccio, B; Raginel, V; Ruehl, I; Tan, J; Todd, B; Weterings, W; Widorski, W

    2011-01-01

    CERN’s LHC injector chain will have to deliver beams with ultimate brilliance as the LHC is heading for increased luminosity in the coming years. In order to overcome bottlenecks in the injector chain, an increase of the beam transfer energy from the CERN Proton Synchrotron Booster (PSB) to the Proton Synchrotron (PS) has been investigated as a possible upgrade scenario. This paper gives an overview of the technical solutions and summarizes the conclusions of the feasibility study.

  15. The database for accelerator control in the CERN PS Complex

    International Nuclear Information System (INIS)

    Cuperus, J.H.

    1987-01-01

    The use of a database started 7 years ago and is an effort to separate logic from data so that programs and routines can do a larger number of operations on data structures without knowing a priori the contents of these structures. It is of great help in coping with the complexities of a system controlling many linked accelerators and storage rings

  16. Operational status of the AGS Booster Main Ring Magnet Power Supply

    International Nuclear Information System (INIS)

    Soukas, A.; Bannon, M.; Geller, J.; McNerney, A.J.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

    1992-01-01

    The Booster is a multipurpose accelerator interposed between a 200 MeV linac, a pair of 15 MV Tandem Van deGraaf accelerators, and the AGS. It can operate on slow cycles of 0.3 Hertz pulse repetition frequency up to a maximum of 7.5 Hertz. The different cycles, from long front porches for long injection or accumulation periods or flattops for slow extraction, to normal fast extraction cycles, accommodate protons, heavy ions (h.i.) and polarized protons. One of the systems enabling the flexible Booster operation is the Main Ring Magnet Power Supply (MRPS) system. It consist of a series connection of six, 1000 volt, multiphase rectifiers together with by pass switches. Two of the six operate at currents up to 6 kA and the rest up to 3 kA. All bypass switches are rated for 6 kA. The system is equipped with passive, damped LCRC filters as well as an active transformer coupled correction system. The MRPS is connected directly to the Long Island 69 Kv bus via a dedicated 20 MVA transformer. The choice of a series of modules enables the very flexible cycle generation and at the same time minimizes the deleterious effects of power factor and harmonics on the ac lines

  17. Psychological factors of professional success of nuclear power plant main control room operators

    Directory of Open Access Journals (Sweden)

    Kosenkov A.A.

    2014-12-01

    Full Text Available Aim: to conduct a comparative analysis of the psychological characteristics of the most and least successful main control room operators. Material and Methods. Two NPP staff groups: the most and least successful main control room operators, who worked in routine operating conditions, were surveyed. Expert evaluation method has been applied to identify the groups. The subjects were administered the Minnesota Multiphasic Personality Inventory (MMPI, Cattell's Sixteen Personality Factor Questionnaire (16PF form A and Raven's Progressive Matrices test. Results. Numerous significant psychological differences between the groups of most and least successful control room operators were obtained: the best operators were significantly more introverted and correctly solved more logical tasks with smaller percentage of mistakes under time pressure than worst ones. Conclusions: 1. The psychodiagnostic methods used in the study were adequate to meet research objective 2. Tendency to introversion, as well as developed the ability to solve logic problems undertime pressure, apparently, are important professional qualities for control room operators. These indicators should be considered in the process of psychological selection and professional guidance of nuclear power plant operators.

  18. Stakeholder involvement in the decommissioning of Trojan and Maine Yankee nuclear power plants

    International Nuclear Information System (INIS)

    Watson, Bruce A.; Orlando, Dominick A.

    2006-01-01

    Trojan Nuclear Plant (Trojan) and Maine Yankee Nuclear Plant (Maine Yankee) were the first two power reactors to complete decommissioning under the U. S. Nuclear Regulatory Commission's (NRC's) License Termination Rule (LTR), 10 CFR Part 20, Subpart E. The respective owners' decisions to decommission the sites resulted in different approaches to both the physical aspects of the decommissioning, and the approach for obtaining approval for completing the decommissioning in accordance with regulations. Being in different States, the two single-unit pressurized water reactor sites had different State requirements and levels of public interest that impacted the decommissioning approaches. This resulted in significant differences in the decommissioning planning, the conduct of decommissioning operations, the volume of low-level radioactive waste, and the final status survey (FSS) program. While both licensees have Independent Spent Fuel Storage Installations (ISFSIs), Trojan obtained a separate license for the ISFSI in accordance with the requirements of 10 CFR Part 72 and terminated its 10 CFR Part 50 license. Maine Yankee elected to reduce the 10 CFR Part 50 license to only the requirements for the ISFSI. While the NRC regulations are flexible and allow different approaches to ISFSI licensing, there are separate licensing requirements that must be addressed. In 10 CFR 50.82, the NRC mandates public participation in the decommissioning process. For Maine Yankee, stakeholder and public input resulted in the licensee entering into an agreement with a citizen group and resulted in State legislation that lowered the dose limit below the NRC radiological criteria of 0.25 milli-Sievert/year (mSv/yr) (25 mrem/yr) in 10 CFR 20.1402 for unrestricted use. The lowering of the radiological criteria resulted in a significant dose modeling effort using site-specific Derived Concentrations Guideline Levels (DCGLs) that were well below the NRC DCGL screening values. This contributed to

  19. Surge currents and voltages at the low voltage power mains during lightning strike to a GSM tower

    Energy Technology Data Exchange (ETDEWEB)

    Markowska, Renata [Bialystok Technical University (Poland)], E-mail: remark@pb.edu.pl

    2007-07-01

    The paper presents the results of numerical calculations of lightning surge currents and voltages in the low voltage power mains system connected to a free standing GSM base station. Direct lightning strike to GSM tower was studied. The analysis concerned the current that flows to the transformer station through AC power mains, the potential difference between the grounding systems of the GSM and the transformer stations and the voltage differences between phase and PE conductors of the power mains underground cable at both the GSM and the transformer sides. The calculations were performed using a numerical program based on the electromagnetic field theory and the method of moments. (author)

  20. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-04-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple “pathways,” or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  1. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    International Nuclear Information System (INIS)

    Kovesdi, Casey Robert; Joe, Jeffrey Clark

    2016-01-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple ''pathways,'' or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  2. Electricity, nuclear power and fuel cycle in OECD countries, main data 1987

    International Nuclear Information System (INIS)

    1987-01-01

    A questionnaire on Electricity Generation. Nuclear Power and Fuel Cycle Data is distributed annually to OECD Member Countries. In the questionnaire of January 1987, countries were asked to provide historical data for 1985 and 1986 and most likely projections up to the year 2005. The replies to the questionnaire or the results of the discussions between national correspondents and the Secretariat are presented in this Booklet. The Secretariat has, in some cases, referred to IEA's electricity-related data and IAEA's nuclear plant data. Where data were still unavailable the Secretariat made estimates based on information from other sources. Data for 1986 are provisional for several countries. The data on electricity generation and electric capacity are presented to the year 2005, and the data on fuel cycle services to the year 2000. The installed nuclear capacity of the OECD countries for the year 2000 is estimated at 340 GWe, a 25 GWe reduction from the estimate in the 1986 Booklet. This reduction is mainly due to revised lower projections of electricity demand. The Addendum contains an analysis of the present and past projections for installed nuclear capacity to 2000. It shows the total capacity of those plants connected to the grid, under construction and firmly planned to be in operation in 2000 as 294 GWe. The new projection of 340 GWe is well above this estimate, indicating that some countries are still planning to expand their nuclear capacities. In only one country does it appear that planned expansion has been affected specifically by the Chernobyl accident. The electricity generation and production data for fuel cycle services refer to those facilities located within the country, and thus exclude imports. The fuel cycle requirements, however, refer to the amounts of fuel cycle materials and services necessary for national nuclear power programmes

  3. Simulation of main steam and feedwater system of full scope simulator for Qinshan 300 MW Nuclear Power Unit

    International Nuclear Information System (INIS)

    Zhao Xiaoyu

    1996-01-01

    The simulation of main steam and feedwater system is the most important and maximal part in secondary circuit model, including all of main steam and feedwater's thermal-hydraulic properties, except heat-exchange of secondary side of steam generator. It simulates main steam header, steam power in each stage of turbine, moisture separator-reheater, deaerator, condenser, high pressure and low pressure heater, auxiliary feedwater and main steam bypass in full scope

  4. A study on the characteristics, predictions and policies of China’s eight main power grids

    International Nuclear Information System (INIS)

    Wang, Jianzhou; Dong, Yao; Jiang, He

    2014-01-01

    Highlights: • Indian blackout is analyzed as a warning for China’s power system. • Issues and recommendations of China’s eight power grids are presented. • Five models are employed for scenario analysis on power generation and consumption. • The optimized combined model outperforms other models. • Methods towards balancing power generation and environmental impacts are proposed. - Abstract: Electricity is an indispensable energy source for modern social and economic development. However, large-scale blackouts can cause incalculable loss to society. In 2012, three major Indian power grids collapsed, resulting in the interruption of the electricity supply to over 600 million people. To avoid an event like that, China needs to forecast the power generation and consumption of eight power grids effectively. This paper first analyzes the characteristics of eight power grids and then proposes a combined model based on three improved grey models optimized by a differential evolution algorithm to predict electricity production and consumption of each power grid. The optimized combined forecasting model provides a better prediction than other models, and it is also the most workable and satisfactory model. Experiment results show electricity production and consumption would increase. In consideration of the real situation and existing problems, some suggestions are proposed. The government could decrease thermal power and exploit renewable energy power, like hydroelectric power, wind power and solar power, to ensure the safe and reliable operation of China’s major power grids and protect environment

  5. Measuring Situation Awareness of Operating Team in Different Main Control Room Environments of Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Seung Woo Lee

    2016-02-01

    Full Text Available Environments in nuclear power plants (NPPs are changing as the design of instrumentation and control systems for NPPs is rapidly moving toward fully digital instrumentation and control, and modern computer techniques are gradually introduced into main control rooms (MCRs. Within the context of these environmental changes, the level of performance of operators in a digital MCR is a major concern. Situation awareness (SA, which is used within human factors research to explain to what extent operators of safety-critical systems know what is transpiring in the system and the environment, is considered a prerequisite factor to guarantee the safe operation of NPPs. However, the safe operation of NPPs can be guaranteed through a team effort. In this regard, the operating team's SA in a conventional and digital MCR should be measured in order to assess whether the new design features implemented in a digital MCR affect this parameter. This paper explains the team SA measurement method used in this study and the results of applying this measurement method to operating teams in different MCR environments. The paper also discusses several empirical lessons learned from the results.

  6. Wastes power generation introduction manual. Main edition; Haikibutsu hatsuden donyu manual. Honpen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    A practical and specific working manual was prepared that satisfies the standards and criteria defined in the relevant law such as the Sanitation and Environment Ordinance No. 249, the guideline for generation of dioxins caused by refuse disposal, and that enables the reports evaluating the wastes quantitatively to be submitted to heads of the local governments when persons in charge of planning the introduction of wastes power generation at local governments discuss the wastes power generation systems. Taking general combustible wastes and sewage sludge treatments as the object, this paper details from the economic performance to size of wastes treatment at the priority limit for the power generation facility introduction. The subject power generation systems include the following: the stoker furnace/separation type ash melting furnace power generation system, the fluidized bed/separation type ash melting furnace power generation system, and the direct type gasification melting furnace power generation system, whose establishment of safety, reliability and stability have been verified by full-size system operation record available at the local governments, the gas turbine re-powering composite type power generation system (gas turbine power plants are installed beside the incineration furnaces) that makes high-efficiency power generation possible, and the RDF power generation system (power generation by mixed combustion with general refuses, and power generation using RDF (refuse derived fuel) exclusive combustion). Other important discussion and assessment items include environment and resource utilization performances. (NEDO)

  7. Overview of electric power industry of main countries in the world

    International Nuclear Information System (INIS)

    2013-01-01

    The electric power supply system, power producer, regulation system, electricity liberalization, power demand and supply, electricity rate, development of electric power sources, nuclear power generation and renewable energy of six countries such as USA, England, German, France, Russia and China are reported. On USA, 3,754 x 10 9 kWh of total electric energy, 104 of nuclear reactors are running and giving careful consideration to safety of the plant. Shale gas production is increasing, and new technology of electric car, smart grid and demand response is developing. On England, 368 x 10 9 kWh of total electric energy, which consisted of 70.4% thermal power, 18.8% nuclear power and 10.8% renewable energy, 18 nuclear reactors are running, but almost nuclear power plants will be closed until 2023. Biomass and wind power have been developed. On German, 609 x 10 9 kWh of total electric energy, 9 nuclear reactors are running but closed till 2022, the renewable energy such as wind power and photovoltaic is introduced. On France, 542 x 10 9 kWh total electric energy, which consisted of 9% hydroelectricity, 9% thermal power, 78% nuclear power and 4% renewable energy. The renewable energy plan is formulated. On Russia, 1,052 x 10 9 kWh total electric energy consisted of 67.8% thermal power, 15.7% hydroelectricity and 16.4% nuclear power, 32 nuclear power plants are running and 9 nuclear reactors building. On China, 4,693 x 10 9 kWh power consumption, 6 nuclear power plants are running to generate 1.85% electric energy, the objects of nuclear power generation and renewable energy were announced. (S.Y.)

  8. Study on the identification of main drivers affecting the performance of human operators during low power and shutdown operation

    International Nuclear Information System (INIS)

    Kim, Ar Ryum; Park, Jinkyun; Kim, Ji Tae; Kim, Jaewhan; Seong, Poong Hyun

    2016-01-01

    Highlights: • The performance of human operator during LPSD operation is significantly important. • Human performance is affected by drivers such as procedure, training, and etc. • Main drivers during LPSD operation at domestic NPPs were suggested. • It is expected that it will be used for estimating human reliability during LPSD operation. - Abstract: In the past, many researchers believed that a reactor during low power and shutdown operation was sufficiently safe. This belief has been changed by the number of accidents during such types of operation, which is significantly high. Also, it was pointed out that one of the main differences between low power and shutdown operation and full power operation is the significance of human action because there are huge amounts of human actions due to extensive maintenance and testing while automatic control and safety functions may be disabled and procedures are insufficient or incomplete. This paper suggests the main drivers in performing human reliability analysis. For this study, we reviewed eight reports relating to human performance during low power and shutdown operation and applied a root cause analysis method for 53 human or human-related events at domestic nuclear power plants to derive the main drivers that affect the occurrence of those events. As a result, several main drivers were derived, such as procedures, training, experience of personnel, and workload/stress. It is expected that these main drivers will be used to perform human reliability analysis for low power and shutdown operation.

  9. Research on characteristics of communication content of operation crew in digital main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Li; Ye Haifeng; Qing Tao; Li Pengcheng

    2015-01-01

    Communication content, communication mode and timeliness of communication are the main three factors that influence the effectiveness of the communication between team members. Based on the work domain analysis to execution of state-oriented procedures (SOP), the assumptions for operation crews' characteristics of the communication content in executing SOP were proposed, which supposed that the power plant status and parameters, power plant system functions and equipment, and SOP as well were the main communication contents. On a full-scope simulator of nuclear power plant, three operation crews performed experiments simulating accident scenarios. The results show that the assumptions of characteristics of the communication content are valid. (authors)

  10. The main safety problems encountered at Creys-Malville power station

    International Nuclear Information System (INIS)

    Saitcevsky, Boris

    1980-01-01

    The 1200 MW. Creys-Malville nuclear power station, situated on the upper Rhone river, in the Isere department, is the largest unit in construction of the fast neutrons sodium-cooled reactor channel. Realized within a European framework, this power station of a specific character, requires special safety dispositions, owing to the utilization of sodium. Safety rests on a thorough preventive system, particularly at the level of the sodium circuits, the shut-down system and the devices for the evacuation of residual power [fr

  11. Mains power synchronous conducted noise measurement in the 2 to 150 kHz band

    NARCIS (Netherlands)

    Keyer, Cornelis H.A.; Buesink, Frederik Johannes Karel; Leferink, Frank Bernardus Johannes

    2016-01-01

    When testing large stationary equipment for EMC compliance, on-site testing is often the only option. In case of a fixed mains connection, use of an artificial mains network is problematic. Within In the framework of an European Research project on EMI testing of large installations, research has

  12. External main-induced events in relation to nuclear power plant siting

    International Nuclear Information System (INIS)

    1981-01-01

    This safety Guide recomments procedures and provides information for use in implementing that part of the code of safety in Nuclear Power Plant Siting (IAEA Safety Series No. 50-C-S) which concerns man-induced events external to the plant, up to the evaluation of corresponding design basis parameters. Like the code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing codes of practice and safety Guides relating to land-based stationary thermal neutron power plants

  13. Performance of the main ring magnet power supply of the KEK 12 GeV proton synchrotron

    International Nuclear Information System (INIS)

    Sato, H.; Sueno, T.; Toyama, T.; Mikawa, Ml; Toda, M.; Matsumoto, S.; Nakano, M.

    1992-01-01

    The main ring magnet power supply of the KEK 12 GeV PS consists of several twelve-pulse thyristor rectifiers with dc filters, of two reactive power compensators with tuned ac harmonic filters and of an analog and digital hybrid control system. In order to obtain well defined parameters-such as absolute precision of beam energy, stable beam position, tracking between focusing and bending fields to fix the betatron tune, stable acquisition of extracted beam spill etc.-one wants to operate this large pulsed power supply with high current reproducibility and low residual current ripple. In this paper, several stabilization techniques are applied in order to meet these requirements

  14. Mechanical seals qualification procedure of the main pumps of nuclear power plants in France

    International Nuclear Information System (INIS)

    Buchdahl, D.; Martin, R.; Girault, J.M.

    1992-12-01

    Many important pumps in the nuclear power plants are equipped with mechanical seals. The good behaviour and reliability of mechanical seals depend specially on the quality and the stability of an interface of several microns. Peripheral speed reaches 50 m/s and pressure 5 MPa, shaft diameter may be 200 mm. Any failure of the mechanical seals may stop the production of electricity or may compromise nuclear safety. As far back as 1970, EDF has conducted qualification actions for the most important mechanical seals in terms of availability and safety. A qualification of mechanical seals needs three steps: - constructor test (tuning) at normal conditions, -qualification test on test rig at EDF/DER (semi-industrial) at normal, exceptional and incidental conditions lasting about 1500 h, - industrial qualification test in nuclear power station over one year. Several supplying sources are absolutely necessary. Any pump may receive mechanical seals from at least two different suppliers. A compromise had to be found to restrict the suppliers' number down to three. This choice concerned three high technology suppliers. A consistent modification procedure had been developed (references file procedure). For each power plant series, about ten types of mechanical seals are concerned. The selection criteria are the higher loads factors P, Vg or the safety related importance. This expensive approach is useful for EDF, many functional failures have been detected before the serial mechanical seals installation in the power plants. (authors). 1 annexe

  15. Maine Yankee Atomic Power Plant. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical energy generated was 5,928,868 MWH with the generator on line 8,347.6 hrs. Information is presented concerning operating experience; specification procedural, and design changes; surveillance tests; containment leak testing; maintenance; licensee events reports; power generation, shutdowns and load reductions; personnel radiation exposures; and primary coolant chemistry

  16. US Mains Stacked Very High Frequency Self-oscillating Resonant Power Converter with Unified Rectifier

    DEFF Research Database (Denmark)

    Pedersen, Jeppe Arnsdorf; Madsen, Mickey Pierre; Mønster, Jakob Døllner

    2016-01-01

    This paper describes a Very High Frequency (VHF) converter made with three Class-E inverters and a single ClassDE rectifier. The converter is designed for the US mains (120 V, 60 Hz) and can deliver 9 W to a 60 V LED. The converter has a switching frequency of 37 MHz and achieves an efficiency...

  17. Vibration measurements at the main gate valves of WWER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Rybak, M.; Matal, O.; Urbanek, M.

    1990-01-01

    The paper summarizes some results of studies concerned with the vibrations of the main gate valves DN 500 during operation of the Dukovany NPP. A diagnostic system for vibration measurements is described. Special attention is paid to the interpretation of the measuring results. Statistical signal analysis is the starting point of deriving parameters for diagostics of impact effects. (author)

  18. 77 FR 47877 - Potential Commercial Leasing for Wind Power on the Outer Continental Shelf (OCS) Offshore Maine...

    Science.gov (United States)

    2012-08-10

    ... Commercial Leasing for Wind Power on the Outer Continental Shelf (OCS) Offshore Maine; Request for Interest... Request for a Commercial OCS Wind Lease, Request for Interest, and Request for Public Comment SUMMARY: The... (Statoil NA) to acquire an OCS wind lease; (2) solicit public input regarding the proposal, its potential...

  19. Main influence factors on the final energy generation cost of a nuclear power plant in comparison with other energy sources

    International Nuclear Information System (INIS)

    Souza, J.A.M. de; Glardon, C.; Schmidt, R.M.

    1981-01-01

    The main factors in the construction and in the operation of nuclear power plants that affect the final energy generation cost are presented. The structure of the energy generation cost, of the nuclear fuel cost and the total investment are studied. (E.G.) [pt

  20. Main problems of increasing labour productivity in the power plant construction

    International Nuclear Information System (INIS)

    Falaleev, P.P.

    1984-01-01

    The reserve for labour productivity growth in power-, industrial- and civil engineering in the USSR Minenergo system are discussed. Such reserve comprises: introduction of effective designs, increase of technological readiness of structures; a higher mechanization level in construction, improvement of industrial organization, economical and social aspects. Decrease of labour inputs in NPP construction will be attained by using unified designs of serial WWER-1000, RBMK-1000- and RBMK-1500 reactors as well as by developing nuclear power construction complexes-industrial-construction enterprises for manufacturing and transport of special structures as well as for performing civil engineering and installation work on the ground part of the reactor building and special structure. Other potentialities for increasing labour productivity in NPP construction are considered

  1. Power-Law-Distributed Dark States are the Main Pathway for Photobleaching of Single Organic Molecules

    OpenAIRE

    Hoogenboom, J.P.; Hoogenboom, Jacob; van Dijk, E.M.H.P.; Hernando Campos, J.; van Hulst, N.F.; Garcia Parajo, M.F.

    2005-01-01

    We exploit the strong excitonic coupling in a superradiant trimer molecule to distinguish between long-lived collective dark states and photobleaching events. The population and depopulation kinetics of the dark states in a single molecule follow power-law statistics over 5 orders of magnitude in time. This result is consistent with the formation of a radical unit via electron tunneling to a time-varying distribution of trapping sites in the surrounding polymer matrix. We furthermore demonstr...

  2. The fast extraction kicker power supply for the main ring of J-PARC

    Energy Technology Data Exchange (ETDEWEB)

    Koseki, Kunio, E-mail: kunio.koseki@kek.jp

    2013-11-21

    An effect induced by parasitic inductance in a pulsed power supply for a fast extraction kicker was studied. The parasitic inductance in high voltage capacitors for a low impedance pulse forming network disturbs a sharp rise of an excitation current. A high voltage capacitor with a coaxial structure to minimize the parasitic inductance is proposed. The effectiveness was confirmed experimentally. An impedance mismatch by a leakage inductance of a pulse transformer in a transmission line was studied. The effect is serious at the flat-top period of the excitation current. By introducing a compensation circuit, which is composed by a capacitor and a resistor, impedance matching was established. The pulsed power supply for the fast extraction kicker was operated at a charging voltage of 30 kV. A required rise time of less than 1.1 μs was achieved. The flatness was also confirmed to be in an acceptable value of less than 1%. -- Highlights: ●An effect by parasitic inductance of the energy storage capacitor of the PFN was studied. ●A faster rise time was achieved by introducing a coaxial structure for the PFN capacitor. ●An impedance mismatch by a leakage inductance of a pulse transformer was studied. ●Serious deterioration of the pulsed waveform was cured by a compensation circuit. ●The pulsed power supply for the fast extraction kicker was developed and operated successfully.

  3. Models of cognitive behavior in nuclear power plant personnel. A feasibility study: main report. Volume 2

    International Nuclear Information System (INIS)

    Woods, D.D.; Roth, E.M.; Hanes, L.F.

    1986-07-01

    This report contains the results of a feasibility study to determine if the current state of models human cognitive activities can serve as the basis for improved techniques for predicting human error in nuclear power plants emergency operations. Based on the answer to this questions, two subsequent phases of research are planned. Phase II is to develop a model of cognitive activities, and Phase III is to test the model. The feasibility study included an analysis of the cognitive activities that occur in emergency operations and an assessment of the modeling concepts/tools available to capture these cognitive activities. The results indicated that a symbolic processing (or artificial intelligence) model of cognitive activities in nuclear power plants is both desirable and feasible. This cognitive model can be built upon the computational framework provided by an existing artificial intelligence system for medical problem solving called Caduceus. The resulting cognitive model will increase the capability to capture the human contribution to risk in probabilistic risk assessments studies. Volume I summarizes the major findings and conclusions of the study. Volume II provides a complete description of the methods and results, including a synthesis of the cognitive activities that occur during emergency operations, and a literature review on cognitive modeling relevant to nuclear power plants. 112 refs., 10 figs

  4. Upgrade of the main ring magnet power supply for the KEK 12GeV proton synchrotron

    International Nuclear Information System (INIS)

    Sato, H.; Sueno, T.; Toyama, T.; Mikawa, M.; Toda, T.; Matsumoto, S.

    1991-01-01

    In order to use the slow extracted beam of the PS more effectively, the period of slow extraction has been extended. In this paper, upgrade of the main ring magnet power supply is described. The main power supply consists of thyrister rectifiers, DC filters, reactive power compensators, AC harmonic filters and control systems. To increase the current capacity during flat top, the rectifiers and transformers were improved. AC network and DC filter were remained as it is, since the acceleration and deceleration times were not varied. Analog control devices and the computer control software have also been improved to realize a 2 sec flat top with a 4 sec repetition rate compared with the former 0.6sec flat top with a 2.5 sec repetition rate

  5. Evaluation of bedrock mainly composed of volcanic aggregate rocks at the Higashidori Nuclear Power Station

    International Nuclear Information System (INIS)

    Hashimoto, Shuichi; Miwa, Tadashi; Nishidachi, Masayuki

    2000-01-01

    When carrying out engineering evaluation on foundation bedrock for important constructions such as nuclear power station, dam, and so forth, it is required as a premise on carrying out various surveys, tests, and analyses to select adequate geological elements, to classify them to some groups capable of regarding as a common engineering property, and to rate them. On a hard bedrock, there is a classification method with relatively higher versatility adding condition of crack and weathering to performances at each site as an index, but on a soft one, most of its classification are carried out individually for its site in response to an index caused by the bedrock itself. Here were shown the results carried out some bedrock classifications on a base of grouping for rock sorts and rock phases, according to some concepts on a draft of the standard on the soft bedrock classification due to the nuclear engineering committee of the Japan Society of Civil Engineers, a reference draft on the soft bedrock classification of the 'Technical indications on seismic resistance design of the nuclear power station' of the Japan Electric Association, (JEAG4601-1987), and so forth. As a result applied the reference draft on the soft bedrock, and so forth to the bedrock at the Higashidori Nuclear Power Station composed of volcanic aggregate rocks of the Miocene epoch of the new Tertiary system, an adequate engineering evaluation was made possible by making grouping of rock sorts and rock phases to a foundation. And, on property evaluation of the quality changed vein, as a result of various tests, appropriate properties could be obtained. (G.K.)

  6. Isolating valve, especially in main-steam pipes of power plants

    International Nuclear Information System (INIS)

    Karpenko, A.N.

    1977-01-01

    The valve for PWRs and BWRs, with diameters up to 1.25 m, for temperatures from -180 0 C to about 600 0 C and pressures up to over 50 bar, is designed for high reliability and long useful life. Two circular valve discs are moved as isolating elements in their plane across the steam direction and brought before the valve seat within a valve chamber. Shortly before reaching this final position, each disc is rotated by a small amount about its axis. Only after reaching the final position a double-wedge, further pushed forward between both discs, produces the necessary contact pressure. By revolving and frictionless closing caking together at high stresses and temperature variation is prevented and permanent tightness assured. The valve body is moved in a cylinder, cast on the valve housing, by means of a stepped piston. Its larger diameter is guided in a second cylinder flanged on above. In the cover of the second cylinder a pilot valve is mounted being controlled over 2 parallel solenoid valves by means of compressed air. In normal operation process steam from the valve chamber serves to move the stepped piston with the valve chamber. On closing of a bore, connecting both cylinder spaces, by the pilot valve the main valve is opened. If the pilot valve is opened the steam through the connecting bore is acting on both piston stages and closing the main valve. On loss of steam (pipe break) or for testing purposes one or the other cylinder space over solenoid valves is acted upon by auxiliary energy or evacuated, the main valve thus being controlled. (HP) [de

  7. Examination of failed studs from No. 2 steam generator at the Maine Yankee Nuclear Power Station

    International Nuclear Information System (INIS)

    Czajkowski, C.

    1983-02-01

    Three studs removed from service on the primary manway cover from steam generator No. 2 of the Maine Yankee station were sent to Brookhaven National Laboratory (BNL) for examination. The examination consisted of visual/dye penetrant examination, optical metallography and Scanning Electron Microscopy/Energy Dispersive Spectroscopy (SEM/EDS) evaluation. One bolt was through cracked and its fracture face was generally transgranular in nature with numerous secondary intergranular cracks. The report concludes that the environmenally assisted cracking of the stud was due to the interaction of the various lubricants used with steam leaks associated with this manway cover

  8. Environmental impact of flooding in the main reservoir of the Churchill Falls Power Plant, Labrador

    International Nuclear Information System (INIS)

    Bajzak, D.; Bruneau, A.A.

    1987-01-01

    The short and long term effects of flooding on the environment, with special emphasis on trees, in the general area of the Churchill Falls hydroelectric project were investigated. A vegetation mapping and inventory was carried out in 1971, followed by the establishment of ground testlines in black spruce, white birch-balsam fir, and burnt (dead) black spruce stands at the rim of the main reservoir before the reservoir was filled in 1972. Additional field observations were made in 1973, 1974 and 1977. It was found that observed changes in the fluctuating water level zone were most significant. Both erosion of soils, mainly due to wave action, and vertical movement of the ice sheet during winter and the spring thaw, contribute to the uprooting of trees in the zone. Trees removed by the process float and under the action of wind and waves drift until trapped in standing trees or until driven ashore or onto dykes. Patches of accumulated driftwood in strips up to 20 m wide are not uncommon, and trees standing in water in protected coves or extensive shallows are not affected by soil erosion and deteriorate only due to fungal attack. 4 refs., 6 figs., 4 tabs

  9. Performance of the cold powered diodes and diode leads in the main magnets of the LHC

    CERN Document Server

    Willering, G P; Bajko, M; Bednarek, M; Bottura, L; Charifoulline, Z; Dahlerup-Petersen, K; Dib, G; D'Angelo, G; Gharib, A; Grand-Clement, L; Izquierdo Bermudez, S; Prin, H; Roger, V; Rowan, S; Savary, F; Tock, J-Ph; Verweij, A

    2015-01-01

    During quench tests in 2011 variations in resistance of an order of magnitude were found in the diode by-pass circuit of the main LHC magnets. An investigation campaign was started to understand the source, the occurrence and the impact of the high resistances. Many tests were performed offline in the SM18 test facility with a focus on the contact resistance of the diode to heat sink contact and the diode wafer temperature. In 2014 the performance of the diodes and diode leads of the main dipole bypass systems in the LHC was assessed during a high current qualification test. In the test a current cycle similar to a magnet circuit discharge from 11 kA with a time constant of 100 s was performed. Resistances of up to 600 μΩ have been found in the diode leads at intermediate current, but in general the high resistances decrease at higher current levels and no sign of overheating of diodes has been seen and the bypass circuit passed the test. In this report the performance of the diodes and in particular the co...

  10. Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D.

    1992-10-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant

  11. Main approaches to choice of decontamination methods in case of nuclear power plant shutdown

    International Nuclear Information System (INIS)

    Tarasov, V.M.; Syrkus, M.N.

    1991-01-01

    Selection criteria for optimal decontamination technology in case of nuclear power plant shutdown are considered. It is shown that technology evaluation from the viewpoint of observance of required precautionary measures is performed during the first stage of operation followed by analysis of process operational characteristics. The next stage relates to risk analysis of equipment, technological process and structure failures. The selection process is followed then according to criteria of decontamination duration, complexity level of control process and availability of qualified personnel, as well as complexity and composition of radioactive waste conditioning. Further follows decontamination technology evaluation from the viewpoint of its impact on personnal health and enviroment. Cost-benefit ratio resulting from introduction of technologies under consideration are determined at the final stage

  12. Low-activation structural ceramic composites for fusion power reactors: materials development and main design issues

    International Nuclear Information System (INIS)

    Perez, A.S.; Le Bars, N.; Giancarli, L.; Proust, E.; Salavy, J.F.

    1994-01-01

    Development of advanced Low-Activation Materials (LAMs) with favourable short-term activation characteristics is discussed, for the use as structural materials in a fusion power reactor (in order to reduce the risk associated with a major accident, in particular those related with radio-isotopes release in the environment), and to try to approach the concept of an inherently safe reactor. LA Ceramics Composites (LACCs) are the most promising LAMs because of their relatively good thermo-mechanical properties. At present, SiC/SiC composite is the only LACC considered by the fusion community, and therefore is the one having the most complete data base. The preliminary design of a breeding blanket using SiC/SiC as structural material indicated that significant improvement of its thermal conductivity is required. (author) 11 refs.; 3 figs

  13. Main ways for solution of nuclear power plant safety in the USSR

    International Nuclear Information System (INIS)

    Sidorenko, V.A.; Kovalevich, O.M.; Kramerov, A.Ya.; Bagdasarov, Yu.E.

    1977-01-01

    In this paper the principles of provisions of nuclear power plant (NPP) safety in the USSR based on the accumulated scientific and engineering experience of design, construction and operating of NPP are discussed. Methods for the decision of the problem were different in various stages of development of nuclear energy and they will be changed in the light of future experience and when the scope of NPP utilization will be broadened. It was formulated the complex of means and ways for providing the real safety of NPP. It includes both the technical and organizing measures and all they are important to solve the NPP safety problem. The first two of these conditions of providing the safety - the high quality of NPP equipment and its constant control during the whole operation of NPP - have to minimize possible failures of power plant elements capable of resulting in an accident conditions. Design and utilization of effective safety systems at NPP and localization systems - these are the next two conditions to provide the safety called upon either to exclude or to attenuate up to the reasonable level the radioactive product yield outside the determined boundaries. The normalization of safety problems and the effective state inspection after keeping the required actions are the next necessary links of this complex called upon to ensure the fulfillment of all safety requirements. The report concerns the realization of formulated procedure to the provision of NPP safety with reactors of WWER and RBM-K types are being put into operation in the Soviet Union. The versatility of approach to the safety provision allows to attain the required safety by various means depending on the type of reactor, its siting and other features concentrating attention to one or another factors. Alongside with the above-mentioned, the paper considers the special requirements and safety measures regarding reactors of next generation such as liquid metal breeders of BN-type and other systems [ru

  14. Practical application of the benchmarking technique to increase reliability and efficiency of power installations and main heat-mechanic equipment of thermal power plants

    Science.gov (United States)

    Rimov, A. A.; Chukanova, T. I.; Trofimov, Yu. V.

    2016-12-01

    facilitating the analysis of the benchmarking results permitting to represent the quality loss of this power installation in the form of the difference between the actual value of the key indicator or comparison indicator and the best quartile of the existing distribution. The uncertainty of the obtained values of the quality loss indicators was evaluated by transforming the standard uncertainties of the input values into the expanded uncertainties of the output values with the confidence level of 95%. The efficiency of the technique is demonstrated in terms of benchmarking of the main thermal and mechanical equipment of the extraction power-generating units T-250 and power installations of the thermal power plants with the main steam pressure 130 atm.

  15. Fundamental features and main problems of nuclear power and radiological safety law

    International Nuclear Information System (INIS)

    Moser, B.

    1981-01-01

    This report deals on a general basis with the legal spheres affected by the utilisation of nuclear energy and protection from ionising radiation. Following a historical survey of the development both in the field of national legisation in Austria and internationally, the five principal legal spheres are discussed in detail. These are administrative law, liability and insurance law, criminal law, constitutional law and international law. In the foreground of discussion is administrative law, which is mainly of a preventive nature. This also comprises radiological safety law. Next in importance is liability and insurance law, which, in contrast to the former, aims at compensation for damage. Criminal law is also intended to have a preventive effect. Finally, the author discusses the peaceful use of nuclear energy in relation to the constitutional law and the international law in force. (Auth.)

  16. Control and reversal of biofilm episode in a nuclear power plant main condenser system

    International Nuclear Information System (INIS)

    Terry, J.P.; Schultz, G.; Ewens, S.

    1996-01-01

    This paper documents a biofilm episode in the main condenser of the Callaway Generating Station. The problem was reversed by the use of oxidizing biocide and a wetting/penetrating agent, along with pH adjustments and other measures. All of the factors leading up to the problem are discussed in detail as are the measures taken to reverse the problem. The most difficult aspect of the problem was identifying the onset of biofilm buildup. The existing background noise in the back pressure and fouling factor data obscured the early stages of the problem and delayed detection and treatment. Alternative monitoring techniques are discussed and the treatment and reversal of the problem are completely documented. The rationale for differentiating between biofouling and deposition caused by inorganic precipitation are discussed

  17. Determination of life-span reserve of main steam ducts in thermal power plants

    International Nuclear Information System (INIS)

    Demian, Mihai; Trusculescu, Marin;

    2002-01-01

    The safe operation of the active vapour ducts requires periodic inspections of the structural conditions and of the properties of the used materials. There are possibilities to establish the structural evolution and that of the materials' properties through destructive or non - destructive methods. Currently, we mostly employ destructive methods by which we can establish the microstructure of the material and the mechanical properties at the temperature of operation for certain periods of time. Lately, we employ non-destructive methods of approaching the structural evolution as a function of operation temperature and work duration. The paper presents the determination of the reserve of the life span of a duct with a 426 mm diameter and 16 mm thickness, which works for 84,556 hours at a temperature of 540 deg. C and a pressure of 2.44 MPa within a thermo - electric power station. By creep trials we established that this duct could also be operated for 16,000 - 28,000 hours. Using the Struers replicas and establishing the 'A' parameter of the degradation of the microstructure in time, we determined a maximum duration of safe exploitation of this duct, of 16,065 hours. Although the non - destructive method is less laborious and does not require sampling from the ducts, it should be adjusted with moderation until there is perfected the methodology of the establishment of the degradation of the grains limits. We recommend that the non - destructive method be available in order to be employed currently with informative character. (authors)

  18. An analysis of the death of main malignant tumor of inhabitants in nuclear power station area

    International Nuclear Information System (INIS)

    Ma Mingqiang; Lu Zunrong; Zheng Wen; Chen Guopei

    1997-01-01

    The authors reported the analysis on the death millimeter situation of inhabitants living around one nuclear power station during pre-operation period of 1988∼1991 and 1992∼1993 operating period. Total surrey population in six years is 2585521 person year, gross malignant tumour death rate is 116.38 x 10 -5 , calibrated death rate is 97.04 x 10 -5 , of which male is 129.20 x 10 -5 , female 65.39 x 10 -5 . An extremely significant difference is noted statistically. Individual annual death rate is 112.00 x 10 -5 , 120.15 x 10 -5 , 125.17 x 10 -5 , 116.45 x 10 -5 , 105.42 x 10 -5 and 119.16 x 10 -5 respectively. The statistical difference was no marked. The highest mortality rate is from the liver cancer, then from the cancer of the lung, of the stomach and of the esophagus. 94 cases died from leukemia with a mortality rate of 3.64 x 10 -5 , and 5 died from thyroid carcinoma, accounting for 0.17% of the total death cases

  19. Main examination results of WWER-1000 fuel after its irradiation in power reactors

    International Nuclear Information System (INIS)

    Bibiliashvili, Yu.; Dubrovin, K.; Vasilchenko, I.; Yenin, A.; Kushmanov, A.; Smirnov, A.; Smirnov, V.

    1994-01-01

    WWER-1000 fuel examination has been undertaken to specify the properties of fuel assembly members by defining the parameters of their materials and their interconnection in power reactor operation conditions. Nine fuel assemblies are examined. The examination program includes: visual inspection, measurement of overall dimensions, eddy-current test, gamma-scanning, X-ray and neutron radiography, analysis of gas pressure and composition inside fuel rods, ceramography/metallography, mass spectrometry, microanalysis and electron microscopy of fuel and fuel claddings. The examination results suggest that WWER-1000 fuel spent at steady-state operation conditions up to 50 Mwd/kg U of burnup is in satisfactory condition. The examination of all types of fuel cladding failures indicates that the reason lies in the interaction of cladding with coolant solid impurities. The nodular cladding corrosion of fuel assembly discharged from the South-Ukrainian NPP is caused by the graphite compounds deposited on the fuel rod. Those deposits are a result of the circulating pump damage and had accidental, non-typical character. Some of the rods were found to have a small cladding 'fretting' of the spacer grid cell material. The values of the majority of parameters determining the fuel efficiency allow to assume that there is a potential for further extension of fuel burnup and operation length. 1 tab., 11 figs

  20. Main examination results of WWER-1000 fuel after its irradiation in power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bibiliashvili, Yu [Vsesoyuznyj Nauchno-Issledovatel` skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation); Dubrovin, K [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation); Vasilchenko, I [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation); Yenin, A; Kushmanov, A [AO Novosibirskij Zavod Khimcontsentratov, Novosibirsk (Russian Federation); Smirnov, A; Smirnov, V [Nauchno-Issledovatel` skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation)

    1994-12-31

    WWER-1000 fuel examination has been undertaken to specify the properties of fuel assembly members by defining the parameters of their materials and their interconnection in power reactor operation conditions. Nine fuel assemblies are examined. The examination program includes: visual inspection, measurement of overall dimensions, eddy-current test, gamma-scanning, X-ray and neutron radiography, analysis of gas pressure and composition inside fuel rods, ceramography/metallography, mass spectrometry, microanalysis and electron microscopy of fuel and fuel claddings. The examination results suggest that WWER-1000 fuel spent at steady-state operation conditions up to 50 Mwd/kg U of burnup is in satisfactory condition. The examination of all types of fuel cladding failures indicates that the reason lies in the interaction of cladding with coolant solid impurities. The nodular cladding corrosion of fuel assembly discharged from the South-Ukrainian NPP is caused by the graphite compounds deposited on the fuel rod. Those deposits are a result of the circulating pump damage and had accidental, non-typical character. Some of the rods were found to have a small cladding `fretting` of the spacer grid cell material. The values of the majority of parameters determining the fuel efficiency allow to assume that there is a potential for further extension of fuel burnup and operation length. 1 tab., 11 figs.

  1. Reliability analysis of operator's monitoring behavior in digital main control room of nuclear power plants and its application

    International Nuclear Information System (INIS)

    Zhang Li; Hu Hong; Li Pengcheng; Jiang Jianjun; Yi Cannan; Chen Qingqing

    2015-01-01

    In order to build a quantitative model to analyze operators' monitoring behavior reliability of digital main control room of nuclear power plants, based on the analysis of the design characteristics of digital main control room of a nuclear power plant and operator's monitoring behavior, and combining with operators' monitoring behavior process, monitoring behavior reliability was divided into three parts including information transfer reliability among screens, inside-screen information sampling reliability and information detection reliability. Quantitative calculation model of information transfer reliability among screens was established based on Senders's monitoring theory; the inside screen information sampling reliability model was established based on the allocation theory of attention resources; and considering the performance shaping factor causality, a fuzzy Bayesian method was presented to quantify information detection reliability and an example of application was given. The results show that the established model of monitoring behavior reliability gives an objective description for monitoring process, which can quantify the monitoring reliability and overcome the shortcomings of traditional methods. Therefore, it provides theoretical support for operator's monitoring behavior reliability analysis in digital main control room of nuclear power plants and improves the precision of human reliability analysis. (authors)

  2. Multi-microprocessor control of the main ring magnet power supply of the 12 GeV KEK proton synchrotron

    International Nuclear Information System (INIS)

    Sueno, T.; Mikawa, K.; Toda, M.; Toyama, T.; Sato, H.; Matsumoto, S.

    1992-01-01

    A general description of the computer control system of the KEK 12 GeV PS main ring magnet power supply is given, including its peripheral devices. The system consists of the main HIDIC-V90/25 CPU and of the input and output controllers HISEC-04M. The main CPU, supervised by UNIX, provides the man-machine interfacing and implements the repetitive control algorithm to correct for any magnet current deviation from reference. Two sub-CPU's are linked by a LAN and supported by a real time multi-task monitor. The output process controller distributes the control patterns to 16-bit DAC's, at 1.67 ms clock period in synchronism with the 3-phase ac line systems. The input controller logs the magnet current and voltage, via 16-bit ADC's at the same clock rate. (author)

  3. Investigation of the impact of main control room digitalization on operators cognitive reliability in nuclear power plants.

    Science.gov (United States)

    Zhou, Yong; Mu, Haiying; Jiang, Jianjun; Zhang, Li

    2012-01-01

    Currently, there is a trend in nuclear power plants (NPPs) toward introducing digital and computer technologies into main control rooms (MCRs). Safe generation of electric power in NPPs requires reliable performance of cognitive tasks such as fault detection, diagnosis, and response planning. The digitalization of MCRs has dramatically changed the whole operating environment, and the ways operators interact with the plant systems. If the design and implementation of the digital technology is incompatible with operators' cognitive characteristics, it may have negative effects on operators' cognitive reliability. Firstly, on the basis of three essential prerequisites for successful cognitive tasks, a causal model is constructed to reveal the typical human performance issues arising from digitalization. The cognitive mechanisms which they impact cognitive reliability are analyzed in detail. Then, Bayesian inference is used to quantify and prioritize the influences of these factors. It suggests that interface management and unbalanced workload distribution have more significant impacts on operators' cognitive reliability.

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

    International Nuclear Information System (INIS)

    Kato, Seiji

    2014-01-01

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

  5. Research on transfer rule of the monitoring of operator in digital main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Li; Li Linfeng; Li Pengcheng; Lu Changshen; Huang Weigang; Dai Zhonghua; Huang Yuanzheng; Chen Qingqing

    2013-01-01

    In the digital main control room of nuclear power plants, monitoring the operating status of the system of reactor is not only one of the most important tasks of the operators, but also the basis and premise of controlling the system of reactor running correctly. After analyzing, inducing, summarizing the data obtained, we found the operators' monitor behavior could be classified as procedure transfer, abnormal transfer, and exchange transfer. The times of exchange transfer is 29% of the total transfer times, abnormal transfer is 14%, regulation transfer is 36%, and others are 21%. (authors)

  6. Main pumps lost incident in the nuclear power plant Atucha I. Modelling with RELAP5/MOD3.2

    International Nuclear Information System (INIS)

    Ventura, M.A.; Rosso, R.D.

    1998-01-01

    Time evolution of natural circulation in the nuclear power plant Atucha I (CNA-I), in a main pumps lost incident because of the lost of external power feed, is analyzed. It leads to a strong stop transient, without an important blow down, from a forced nominal flow to a natural circulation one. The results are obtained from RELAP5/MOD3.2 code's modeling. The study is based on the refrigeration conditions analysis, during the first minutes of the reactor out of service. Previously to the transient, work had been done to obtain the plant steady state, with design parameters in operation conditions at 100 % of power. The object is that the actual plant state would be represented. In this way, each plant part (steam generators, reactor, pressurizer, pumps) had been modeled in separated form with the appropriate boundary conditions, to be used in the whole circuit simulation. The developed model, had been validated making use of the comparison between the values obtained to the principal thermodynamic parameters with the plant recorded values, in the same incident. The results are satisfactory in a way. On the other hand, it has suggested some modeling changes. The RELAP5/MOD3.2 capability to model the thermodynamic phenomena in a PHWR plant has been verified when, according to the mentioned incident, the flow pass from a nominal forced flow, to one which is governed by natural circulation, still with the CNA-I untypical design conditions. (author) [es

  7. Main corrective measures in an early phase of nuclear power plants’ preparation for safe long term operation

    Energy Technology Data Exchange (ETDEWEB)

    Krivanek, Robert, E-mail: r.krivanek@iaea.org [International Atomic Energy Agency (IAEA), Department of Nuclear Safety and Security, Operational Safety Section, Vienna 1400 (Austria); Fiedler, Jan, E-mail: fiedler@fme.vutbr.cz [University of Technology Brno, Faculty of Mechanical Engineering, Energy Institute, Technická 2896/2, 616 69 Brno (Czech Republic)

    2017-05-15

    Highlights: • Results of SALTO missions provide the most important issues for safe long term operation (LTO) of nuclear power plants. • The most important technical corrective measures in an early phase of preparation for safe LTO are described. • Their satisfactory resolution creates a basis for further activities to demonstrate preparedness for safe LTO. - Abstract: This paper presents the analysis of main technical deficiencies of nuclear power plants (NPPs) in preparedness for safe long term operation (LTO) and the main corrective measures in an early phase of preparation for safe LTO of NPPs. It focuses on technical aspects connected with management of physical ageing of NPP structures, systems and components (SSCs). It uses as a basis results of IAEA SALTO missions performed between 2005 and 2016 (see also paper NED8805 in Nuclear Engineering and Design in May 2016) and the personal experiences of the authors with preparation of NPPs for safe LTO. This paper does not discuss other important aspects of safe LTO of NPPs, e.g. national nuclear energy policies, compliance of NPPs with the latest international requirements on design, obsolescence, environmental impact and economic aspects of LTO. Chapter 1 provides a brief introduction of the current status of the NPP’ fleet in connection with LTO. Chapter 2 provides an overview of SALTO peer review service results with a focus on deficiencies related to physical ageing of safety SSCs and a demonstration that SSCs will perform their safety function during the intended period of LTO. Chapter 3 discusses the main corrective measures which NPPs typically face during the preparation for demonstration of safe LTO. Chapter 4 summarizes the current status of the NPP’ fleet in connection with LTO and outlines further steps needed in preparation for safe LTO.

  8. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    International Nuclear Information System (INIS)

    Yang, Chih Wei; Cheng, Tsung Chieh; Lin, Chiuhsiang Joe

    2011-01-01

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner

  9. Main research results in the field of nuclear power engineering of the Nuclear Reactors and Thermal Physics Institute in 2014

    International Nuclear Information System (INIS)

    Trufanov, A.A.; Orlov, Yu.I.; Sorokin, A.P.; Chernonog, V.L.

    2015-01-01

    The main results of scientific and technological activities for last years of the Nuclear Reactors and Thermal Physics Institute FSUE SSC RF - IPPE in solving problems of nuclear power engineering are presented. The work have been carried out on the following problems: justification of research and development solutions and safety of NPPs with fast reactors of new generation with sodium (BN-1200, MBIR) and lead (BREST-OD-300) coolants, justification of safety of operating and advanced NPPs with WWER reactor facilities (WWER-1000, AEhS 2006, WWER-TOI), development and benchmarking of computational codes, research and development support of Beloyarsk-3 (BN-600) and Bilibino (BN-800) NPPs operation, decommissioning of AM and BR-10 research reactors, pilot scientific studies (WWER-SKD, ITER), international scientific and technical cooperation. Problems for further investigations are charted [ru

  10. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih Wei; Cheng, Tsung Chieh [Institute of Nuclear Energy Research, Taoyuan (China); Lin, Chiuhsiang Joe [Chung-Yuan Christian University, Chung Li (China)

    2011-08-15

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner.

  11. Determining the residual lifetime for the main RBMK components in frame of life extension of power units

    International Nuclear Information System (INIS)

    Baldin, V.D.; Petrov, A.A.; Potapov, A.A.

    2005-01-01

    At present time 11 power units of NPPs with RBMK reactors produce annually 140 billion kWh of electricity, which is about half of all electricity generated at Russian NPPs. Commissioned during the period of 1973 to 1990, they have the specified service life of 30 years. The power units have been regularly upgraded during operation to raise their safety and reliability. As the result now they meet modem requirements in terms of safety and their lifetime can considerably exceed their specified service life. The task of the plant life extension becomes more urgent. The main nonreplaceable RBMK reactor components that determine the reactor life, are graphite stack and metal support structures. The aging of these structures is monitored and the structures residual lifetime is predicted in accordance with procedures approved by regulatory authorities. The lead unit among all RBMK power units is Leningrad NPP Unit 1 commissioned in 1973. A complex of activities was performed for this power unit in 2002-2003 to prove the feasibility of its life extension. In terms of defining the residual lifetime of the reactor components, the activities were performed in three major areas: - examination of the state of the reactor structures; - materials studies of irradiated metal and graphite specimens in hot chambers; - performing the calculation and prediction evaluations. The results of examining the metal structures and studying specimens have shown that: 1)The metal and the welds do not have visible defects. The state of protective coatings is largely satisfactory. 2)The ultimate strength and hardness of steel have grown. 3)The brittle fracture transition temperature shift is at the allowable level. 4)The leak-tightness of the metal structures has not been violated. The results of the graphite stack examination have shown that the graphite is at the hardening stage. No tendency for deterioration of mechanical properties has been recorded. According to the results of measuring the

  12. Development of task analysis method for operator tasks in main control room of an advanced nuclear power plant

    International Nuclear Information System (INIS)

    Lin Chiuhsiangloe; Hsieh Tsungling

    2016-01-01

    Task analysis methods provide an insight for quantitative and qualitative predictions of how people will use a proposed system, though the different versions have different emphases. Most of the methods can attest to the coverage of the functionality of a system and all provide estimates of task performance time. However, most of the tasks that operators deal with in a digital work environment in the main control room of an advanced nuclear power plant require high mental activity. Such mental tasks overlap and must be dealt with at the same time; most of them can be assumed to be highly parallel in nature. Therefore, the primary aim to be addressed in this paper was to develop a method that adopts CPM-GOMS (cognitive perceptual motor-goals operators methods selection rules) as the basic pattern of mental task analysis for the advanced main control room. A within-subjects experiment design was used to examine the validity of the modified CPM-GOMS. Thirty participants participated in two task types, which included high- and low-compatibility types. The results indicated that the performance was significantly higher on the high-compatibility task type than on the low-compatibility task type; that is, the modified CPM-GOMS could distinguish the difference between high- and low-compatibility mental tasks. (author)

  13. An Investigation for Arranging the Video Display Unit Information in a Main Control Room of Advanced Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Hsu, Chong Cheng; Yang, Chih Wei [Institute of Nuclear Energy Research, Atomic Energy Council, Taoyuan (China)

    2014-08-15

    Current digital instrumentation and control and main control room (MCR) technology has extended the capability of integrating information from numerous plant systems and transmitting needed information to operations personnel in a timely manner that could not be envisioned when previous generation plants were designed and built. A MCR operator can complete all necessary operating actions on the video display unit (VDU). It is extremely flexible and convenient for operators to select and to control the system display on the screen. However, a high degree of digitalization has some risks. For example, in nuclear power plants, failures in the instrumentation and control devices could stop the operation of the plant. Human factors engineering (HFE) approaches would be a manner to solve this problem. Under HFE considerations, there exists 'population stereotype' for operation. That is, the operator is used to operating a specific display on the specific VDU for operation. Under emergency conditions, there is possibility that the operator will response with this habit population stereotype, and not be aware that the current situation has already changed. Accordingly, the advanced nuclear power plant should establish the MCR VDU configuration plan to meet the consistent teamwork goal under normal operation, transient and accident conditions. On the other hand, the advanced nuclear power plant should establish the human factors verification and validation plan of the MCR VDU configuration to verify and validate the configuration of the MCR VDUs, and to ensure that the MCR VDU configuration allows the operator shift to meet the HFE consideration and the consistent teamwork goal under normal operation, transient and accident conditions. This paper is one of the HF V V plans of the MCR VDU configuration of the advanced nuclear power plant. The purpose of this study is to confirm whether the VDU configuration meets the human factors principles and the consistent

  14. An Investigation for Arranging the Video Display Unit Information in a Main Control Room of Advanced Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hsu, Chong Cheng; Yang, Chih Wei

    2014-01-01

    Current digital instrumentation and control and main control room (MCR) technology has extended the capability of integrating information from numerous plant systems and transmitting needed information to operations personnel in a timely manner that could not be envisioned when previous generation plants were designed and built. A MCR operator can complete all necessary operating actions on the video display unit (VDU). It is extremely flexible and convenient for operators to select and to control the system display on the screen. However, a high degree of digitalization has some risks. For example, in nuclear power plants, failures in the instrumentation and control devices could stop the operation of the plant. Human factors engineering (HFE) approaches would be a manner to solve this problem. Under HFE considerations, there exists 'population stereotype' for operation. That is, the operator is used to operating a specific display on the specific VDU for operation. Under emergency conditions, there is possibility that the operator will response with this habit population stereotype, and not be aware that the current situation has already changed. Accordingly, the advanced nuclear power plant should establish the MCR VDU configuration plan to meet the consistent teamwork goal under normal operation, transient and accident conditions. On the other hand, the advanced nuclear power plant should establish the human factors verification and validation plan of the MCR VDU configuration to verify and validate the configuration of the MCR VDUs, and to ensure that the MCR VDU configuration allows the operator shift to meet the HFE consideration and the consistent teamwork goal under normal operation, transient and accident conditions. This paper is one of the HF V V plans of the MCR VDU configuration of the advanced nuclear power plant. The purpose of this study is to confirm whether the VDU configuration meets the human factors principles and the consistent

  15. The influence and evaluation of different virtual reality presentations for the main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Rouwen; Lin Chiuhsiang Joe; Lin Shiaufeng; Yang Chihwei; Cheng Tsungchieh; Yang Lichen

    2011-01-01

    Certainly, a nuclear power plant (NPP) is a complex system and requires high reliability. Engineering technology plays an important role in NPP that requires complex technical equipment and interfaces in order to achieve public security and working safety. Through training, operators can understand the nuclear power system and further establish the fit between human operators and the system, in order to reduce human errors and to ensure the working safety of the control room of NPP. However, the operator trainings for the control room of NPP are difficult and time-consuming. Virtual control room is thus developed using the virtual reality (VR) technology to help the training process. Presently several researches have developed virtual system for NPP for the purpose of training. However, whether the virtual training system for the control room of NPP can give users realistic immersive context as in the real environment is unknown. Whether these virtual systems are helpful in training performance are yet to be confirmed. For this reason, the control room of Lung-Men NPP of Taiwan was constructed with VR technology in this study in order to compare the performances of two VR representation methods (Desktop VR and Project VR). A searching task was planned in which the operators have to find out the objects appointed by the experimenter in the virtual interface of the main control room. The time to complete the task was collected as dependent variables in this experiment. The subjects have to complete the questionnaire that was developed for evaluating the usability of the virtual interface of MRC after finishing the experiment. The result showed that the performance of the virtual interface of NPP presented by the VR projector was better than the desktop. (author)

  16. ANALYSIS OF SUFFICIENCY OF THE BEARING CAPACITY OF BUILDING STRUCTURES OF OPERATING SITES OF MAIN BUILDINGS OF THERMAL POWER PLANTS

    Directory of Open Access Journals (Sweden)

    Alekseeva Ekaterina Leonidovna

    2012-10-01

    Full Text Available Upon examination of eleven main buildings of power plants, analysis of defects and damages of building structures was performed. Thereafter, the damageability of principal bearing structures of main buildings of thermal plants was analyzed. It was identified that the fastest growing defects and damages were concentrated in the structures of operating sites. The research of the rate of development of the most frequent damages and defects made it possible to conclude that internal corrosion of the reinforcing steel was the most dangerous defect, as far as the reinforced concrete elements of operating sites were concerned. Methods of mathematical statistics were applied to identify the reinforcing steel development pattern inside reinforced concrete elements of floors of operating sites. It was identified that the probability of corrosion of reinforced concrete elements of operating sites was distributed in accordance with the demonstrative law. Based on these data, calculation of strength of reinforced concrete slabs and metal beams was performed in terms of their regular sections, given the natural loads and the realistic condition of structures. As a result, dependence between the bearing capacity reserve ratio and the corrosion development pattern was identified for reinforced concrete slabs and metal beams of operating sites. In order to analyze the sufficiency of the bearing capacity of building structures of operating sites in relation to their time in commission, equations were derived to identify the nature of dependence between the sufficiency of the bearing capacity of reinforced concrete slabs and metal beams of the operating sites and their time in commission.

  17. Explorer-II: Wireless Self-Powered Visual and NDE Robotic Inspection System for Live Gas Distribution Mains

    Energy Technology Data Exchange (ETDEWEB)

    Carnegie Mellon University

    2008-09-30

    Carnegie Mellon University (CMU) under contract from Department of Energy/National Energy Technology Laboratory (DoE/NETL) and co-funding from the Northeast Gas Association (NGA), has completed the overall system design, field-trial and Magnetic Flux Leakage (MFL) sensor evaluation program for the next-generation Explorer-II (X-II) live gas main Non-destructive Evaluation (NDE) and visual inspection robot platform. The design is based on the Explorer-I prototype which was built and field-tested under a prior (also DoE- and NGA co-funded) program, and served as the validation that self-powered robots under wireless control could access and navigate live natural gas distribution mains. The X-II system design ({approx}8 ft. and 66 lbs.) was heavily based on the X-I design, yet was substantially expanded to allow the addition of NDE sensor systems (while retaining its visual inspection capability), making it a modular system, and expanding its ability to operate at pressures up to 750 psig (high-pressure and unpiggable steel-pipe distribution mains). A new electronics architecture and on-board software kernel were added to again improve system performance. A locating sonde system was integrated to allow for absolute position-referencing during inspection (coupled with external differential GPS) and emergency-locating. The power system was upgraded to utilize lithium-based battery-cells for an increase in mission-time. The resulting robot-train system with CAD renderings of the individual modules. The system architecture now relies on a dual set of end camera-modules to house the 32-bit processors (Single-Board Computer or SBC) as well as the imaging and wireless (off-board) and CAN-based (on-board) communication hardware and software systems (as well as the sonde-coil and -electronics). The drive-module (2 ea.) are still responsible for bracing (and centering) to drive in push/pull fashion the robot train into and through the pipes and obstacles. The steering modules

  18. Main conditions and effectiveness of gas fuel use for powering of dual fuel IC self-ignition engine

    Directory of Open Access Journals (Sweden)

    Stefan POSTRZEDNIK

    2015-09-01

    Full Text Available Internal combustion engines are fuelled mostly with liquid fuels (gasoline, diesel. Nowadays the gaseous fuels are applied as driving fuel of combustion engines. In case of spark ignition engines the liquid fuel (petrol can be totally replaced by the gas fuels. This possibility in case of compression engines is essentially restricted through the higher self-ignition temperatures of the combustible gases in comparison to classical diesel oil. Solution if this problem can be achieved by using of the dual fuel system, where for ignition of the prepared fuel gas - air mixture a specified amount of the liquid fuel (diesel oil should be additionally injected into the combustion chamber. For assurance that the combustion process proceeds without mistakes and completely, some basic conditions should be satisfied. In the frame of this work, three main aspects of this problem are taken into account: a. filling efficiency of the engine, b. stoichiometry of the combustion, c. performance of mechanical parameters (torque, power. A complex analysis of these conditions has been done and some achieved important results are presented in the paper.

  19. Power Management of the DC Bus Connected Converters in a Hybrid AC/DC Microgrid Tied to the Main Grid

    Directory of Open Access Journals (Sweden)

    Robert Antonio Salas-Puente

    2018-03-01

    Full Text Available In this paper, a centralized control strategy for the efficient power management of power converters composing a hybrid AC/DC microgrid is explained. The study is focused on the converters connected to the DC bus. The proposed power management algorithm is implemented in a microgrid central processor which is based on assigning several operation functions to each of the generators, loads and energy storage systems in the microgrid. The power flows between the DC and AC buses are studied in several operational scenarios to verify the proposed control. Experimental and simulation results demonstrate that the algorithm allows control of the power dispatch inside the microgrid properly by performing the following tasks: communication among power converters, the grid operator and loads; connection and disconnection of loads; control of the power exchange between the distributed generators and the energy storage system and, finally, supervision of the power dispatch limit set by the grid operator.

  20. Trend of nuclear power development in main countries and perspective of nuclear industry after the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Murakami, Tomoko

    2011-01-01

    Fukushima Daiichi Accident occurred in March 11, 2011 was of highest interest in the world and had been reported worldwide from relevant Japanese organizations almost in real time just after happened. This article overviewed five month's response of government and energy related organization of each country and international agency and summarized effects of the accident on nuclear power in energy policy of each country as well as perspective of nuclear industry responded to change of market trend. After the accident, basic policy to regard nuclear power as important was maintained with enhancing reactor safety against extreme events in countries choosing nuclear power as important and requisite energy and there appeared such a trend of nuclear power phase-out in countries promoting nuclear power prudently. Choice of nuclear power would be decided on energy state of each country and was not affected before and after the accident. Trend of nuclear business was closely related with that of market and no fundamental change was observed although some industries with revenue from business in nuclear power phase-out country or cancelled project after the accident were obliged to be affected. (T. Tanaka)

  1. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary: main report

    International Nuclear Information System (INIS)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks

  2. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  3. The main methods of solving the problem of radioactive waste management from nuclear power stations and spent fuel reprocessing plants in the USSR

    International Nuclear Information System (INIS)

    1978-09-01

    The main directions of solving the problem of radioactive waste management from nuclear power stations and radiochemical plants, the aspects of gaseous waste management, liquid HLW storage in vessels and the problems of heat removal during storage of vitrified HLW in surface storages are considered. The main problems arising during fine decontamination of gaseous discharges from nuclear power stations and reprocessing plants are discussed. The migration of fission products in the environment and technical aspects of their capture from gaseous discharges are also considered

  4. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    International Nuclear Information System (INIS)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee

    2004-02-01

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA

  5. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An Kang Il; Hong, Suk Young; Lee, Jeong Soo; Lee, Kwang Yeol; Shin, Sun Hee; Lee, Chun Wha; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2003-03-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following: development of H/W that is necessary to acquire operating real time data of heating and hydraulic power, selection of a safety variable about major system by each type (the fourth unit), communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server, development of connecting database for controlling and storing of heating and hydraulic power operating data, real time monitoring system development based on web using JAVA.

  6. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA.

  7. The selection of flying roller as an effort to increase the power of scooter-matic as the main power of centrifugal pump for fire fighter motor cycle

    Science.gov (United States)

    Hadi Sutrisno, Himawan

    2018-03-01

    In densely populated settlements, fires often occur and cause losses. In some instances, the process of the occurrence of fires takes place so quickly that to reduce and avoid the occurrence of a fire disaster effort is required in accordance with the existing environmental condition. Fire fighter motorcycle by using motorcycle scooter-matic is considered suitable as one alternative to combating fire hazard in densely populated residential settlements. The use of motorcycle engines as the driving force of the pump often leads to unstable and not optimum power. Thus, the water spray on the centrifugal pump also becomes not maximum. To increase the engine power at scooter-matic engine idle rotation (700-2000 rpm), then the flying roller replacement with certain mass weight becomes an option. By selecting a 10 to 14 gram flying roller mass, the power analysis using a dynotest engine produces several variations. Of the calculation, the mass of a 14 gram flying roller provides a significant increase in motor power on the upper rotation. Meanwhile, on the lower power rotation using a flying roller with a mass of 10 grams provides an increase in power compared to a standard flying roller on a scooter matic motor engine. As a reference to the use of scooter-matic motor power as the pump power, the result of use of the flying roller with a mass of 10 grams becomes the best option.

  8. Development of 20 kW input power coupler for 1.3 GHz ERL main linac. Component test at 30 kW IOT test stand

    International Nuclear Information System (INIS)

    Sakai, Hiroshi; Umemori, Kensei; Sakanaka, Shogo; Takahashi, Takeshi; Furuya, Takaaki; Shinoe, Kenji; Ishii, Atsushi; Nakamura, Norio; Sawamura, Masaru

    2009-01-01

    We started to develop an input coupler for a 1.3 GHz ERL superconducting cavity. Required input power is about 20 kW for the cavity acceleration field of 20 MV/m and the beam current of 100 mA in energy recovery operation. The input coupler is designed based on the STF-BL input coupler and some modifications are applied to the design for the CW 20 kW power operation. We fabricated input coupler components such as ceramic windows and bellows and carried out the high-power test of the components by using a 30 kW IOT power source and a test stand constructed for the highpower test. In this report, we mainly describe the results of the high-power test of ceramic window and bellows. (author)

  9. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Maine Yankee nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.; Mayn, B.G.

    1979-08-01

    This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Maine Yankee nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

  10. Assessment of RELAP5/MOD2 against a main feedwater turbopump trip transient in the Vandellos II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Llopis, C.; Casals, A.; Perez, J.; Mendizabal, R.

    1993-12-01

    The Consejo de Seguridad Nuclear (CSN) and the Asociacion Nuclear Vandellos (ANV) have developed a model of Vandellos II Nuclear Power Plant. The ANV collaboration consisted in the supply of design and actual data, the cooperation in the simulation of the control systems and other model components, as well as in the results analysis. The obtained model has been assessed against the following transients occurred in plant: A trip from the 100% power level (CSN); a load rejection from 100% to 50% (CSN); a load rejection from 75% to 65% (ANV); and, a feedwater turbopump trip (ANV). This copy is a report of the feedwater turbopump trip transient simulation. This transient actually occurred in the plant on June 19, 1989

  11. Intermediate size LWR plant study for process heat plus power: main report. Volume 2 of 3 volumes

    International Nuclear Information System (INIS)

    Head, M.A.

    1977-01-01

    The study of process heat-plus-power generation from 900 to 1200 MWt BWRs was initiated by analysis of the smaller BWR plants, which have substantial operating experience. The Muhleberg 306 MWe BWR (four years of operation and 74% capacity factor) and the Humboldt Bay, natural circulation system (ten years of operation and 69% capacity factor) were identified as leading plants. The Muhleberg design, cost, and operating data therefore were analyzed in further detail. Analysis was also conducted on the Humboldt Bay unit, even though its 63 MHe size is not directly applicable. In this case, attention was focused on the potential for updating the natural circulation concept to the 1000 MWt level. Cost analyses were conducted on actual costs incurred, including correction indices for escalation to 1976. The changes in licensing requirements were evaluated and their cost impact estimated. Some indication of the economies possible through standardization and use of modular construction were estimated by reference to earlier work under the nuclear park (or energy center) study program. Consideration was directed to the organizational needs for design, construction, and project management, if an effective program were to be undertaken. The importance of a demonstration project as a means of establishing a design standard for duplication or replication (and the program requirements to bring about such a demonstration project) were then addressed. Finally, capital costs developed from the actual plant costs were used to determine power generation costs

  12. Power

    DEFF Research Database (Denmark)

    Elmholdt, Claus Westergård; Fogsgaard, Morten

    2016-01-01

    and creativity suggests that when managers give people the opportunity to gain power and explicate that there is reason to be more creative, people will show a boost in creative behaviour. Moreover, this process works best in unstable power hierarchies, which implies that power is treated as a negotiable....... It is thus a central point that power is not necessarily something that breaks down and represses. On the contrary, an explicit focus on the dynamics of power in relation to creativity can be productive for the organisation. Our main focus is to elaborate the implications of this for practice and theory...

  13. Trend and pattern analysis of failures of main feedwater system components in United States commercial nuclear power plants

    International Nuclear Information System (INIS)

    Gentillon, C.D.; Meachum, T.R.; Brady, B.M.

    1987-01-01

    The goal of the trend and pattern analysis of MFW (main feedwater) component failure data is to identify component attributes that are associated with relatively high incidences of failure. Manufacturer, valve type, and pump rotational speed are examples of component attributes under study; in addition, the pattern of failures among NPP units is studied. A series of statistical methods is applied to identify trends and patterns in failures and trends in occurrences in time with regard to these component attributes or variables. This process is followed by an engineering evaluation of the statistical results. In the remainder of this paper, the characteristics of the NPRDS that facilitate its use in reliability and risk studies are highlighted, the analysis methods are briefly described, and the lessons learned thus far for improving MFW system availability and reliability are summarized (orig./GL)

  14. General design and main problems of a gas-heavy-water power reactor contained in a pressure vessel

    International Nuclear Information System (INIS)

    Roche, R.; Gaudez, J.C.

    1964-01-01

    In the framework of research carried out on a CO 2 -cooled power reactor moderated by heavy water, the so-called 'pressure vessel' solution involves the total integration of the core, of the primary circuit (exchanges and blowers) and of the fuel handling machine inside a single, strong, sealed vessel made of pre-stressed concrete. A vertical design has been chosen: the handling 'attic' is placed above the core, the exchanges being underneath. This solution makes it possible to standardize the type of reactor which is moderated by heavy-water or graphite and cooled by a downward stream of carbon dioxide gas; it has certain advantages and disadvantages with respect to the pressure tube solution and these are considered in detail in this report. Extrapolation presents in particular.problems due specifically to the heavy water (for example its cooling,its purification, the balancing of the pressures of the heavy water and of the gas, the assembling of the internal structures, the height of the attic, etc. (authors) [fr

  15. Investigation of the Temperature Sensors Accuracy in the Temperature Monitoring System for the Welded Joints of the Industrial Power Supply Main Busways

    Science.gov (United States)

    Grivennaya, N. V.; Bazhenov, A. V.; Bondareva, G. A.; Malygin, S. V.; Knyaginin, A. A.

    2018-01-01

    The article is devoted to the substantiation of the technical solution of the remote monitoring system for the temperature changes of main and branch busways of power supply to industrial enterprises of increased environmental danger. When monitoring the temperature of trunk buses of AC mains up to 1000 V, heated by an electric current, errors occur due to various factors. Studies have been carried out to evaluate the effect of temperature of surrounding objects (including neighboring busbars) on the accuracy of temperature measurements. Conclusions are made about the possibility of using alternative versions of temperature sensors as the basis of the monitoring system.

  16. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report

  17. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

  18. Kozloduy Nuclear Power Plant (Unit 1 and 2). Proposed modifications to increase the seismic capability of equipment and main structures

    International Nuclear Information System (INIS)

    Ordonez Villalobos, A.; Monette, P.R.

    1993-01-01

    Within the framework of the European Community's PHARE Programme of improvement to facilities, their operating systems, equipment and buildings of the Kozloduy NPP in Bulgaria, plant safety during seismic events is considered to be an issue of overriding importance, especially in view of the earthquakes the region suffered during the last decade. Westinghouse Energy Systems International (WESI) and Empresarios Agrupados (EA) have initiated an intensive programme for physical upgrading of equipment with a view to augmenting its seismic capability and, at the same time, to studying design modifications in the diesel-generator buildings, pump house and main building structures (turbines, electrical building). The implementation of these modifications requires an in situ inspection of the real conditions of the various elements, analyses, conceptual design and detail engineering, all of which has to be done in short periods of time using resources available at the plant. This activity is performed by the companies mentioned above, with the collaboration of two engineering companies, Energoproekt of Bulgaria and INITEC of Spain. This paper describes the activities developed and the treatment given to the various aspects of improvement of the seismic capability of equipment and structures. (author)

  19. Impact of the Voltage Transients after a Fast Power Abort on the Quench Detection System in the LHC Main Dipole Chain

    CERN Document Server

    Ravaioli, E; Formenti, F; Montabonnet, V; Pojer, M; Schmidt, R; Siemko, A; Solfaroli Camillocci, A; Steckert, J; Thiesen, H; Verweij, A

    2012-01-01

    A Fast Power Abort in the LHC superconducting main dipole circuit consists in the switch-off of the power converter and the opening of the two energy-extraction switches. Each energy-extraction unit is composed of redundant electromechanical breakers, which are opened to force the current through an extraction resistor. When a switch is opened arcing occurs in the switch and a voltage of up to 1 kV builds up across the extraction resistor with a typical ramp rate of about 80 kV/s. The subsequent voltage transient propagates through the chain of 154 dipoles and superposes on the voltage waves caused by the switch-off of the power converter. The resulting effect caused intermittent triggering of the quench protection systems along with heater firings in the magnets when the transient occurred during a ramp of the current. A delay between power converter switch-off and opening of the energy-extraction switches was introduced to prevent this effect. Furthermore, the output filters of the power converters were mod...

  20. Measurement of the mean radial position of a lead ion beam in the CERN PS

    CERN Document Server

    Belleman, J; González, J; Johnston, S; Schulte, E C; Thivent, E

    1996-01-01

    The intensity of the lead ion beam in the PS, nominally 4×108 charges of Pb53+ per bunch, is too low for the closed orbit measurement system. However, for successful acceleration it is sufficient to know the mean radial position (MRP). A system was thus designed for simultaneous acquisition of revolution frequency and magnetic field. The frequency measurement uses a direct digital synthesiser (DDS), phase-locked to the beam signal from a special high-sensitivity pick-up. The magnetic field is obtained from the so-called B-train. From these two values, the MRP is calculated. The precision depends on the frequency measurement and on the accuracy of the value for the magnetic field. Furthermore, exact knowledge of the transition energy is essential. This paper describes the hardware and software developed for the MRP system, and discusses the issue of calibration, with a proton beam, of the B measurement.

  1. Stabilizing effect of a double-harmonic RF system in the CERN PS

    International Nuclear Information System (INIS)

    Bhat, C.; Caspers, F.; Damerau, H.; Hancock, S.; Mahner, E.; Zimmermann, F.

    2009-01-01

    Motivated by the discussions on scenarios for LHC upgrades, beam studies on the stability of flat bunches in a double-harmonic RF system have been conducted in the CERN Proton Synchrotron (PS). Injecting nearly nominal LHC beam intensity per cycle, 18 bunches are accelerated on harmonic h = 21 to 26GeV with the 10MHz RF system. On the flat-top, all bunches are then transformed to flat bunches by adiabatically adding RF voltage at h = 42 from a 20 MHz cavity in anti-phase to the h = 21 system. The voltage ratio V (h42)/V (h21) of about 0.5 was set according to simulations. For the next 140 ms, longitudinal profiles show stable bunches in the double-harmonic RF bucket until extraction. Without the second harmonic component, coupled-bunch oscillations are observed. The flatness of the bunches along the batch is analyzed as a measure of the relative phase error between the RF systems due to beam loading. The results of beam dynamics simulations and their comparison with the measured data are presented

  2. Workstations as consoles for the CERN-PS complex, setting-up the environment

    International Nuclear Information System (INIS)

    Antonsanti, P.; Arruat, M.; Bouche, J.M.; Cons, L.; Deloose, Y.; Di Maio, F.

    1992-01-01

    Within the framework of the rejuvenation project of the CERN control systems, commercial workstations have to replace existing home-designed operator consoles. RISC-based workstations with UNIX, X-window TM and OSF/Motif TM have been introduced for the control of the PS complex. The first versions of general functionalities like synoptic display, program selection and control panels have been implemented and the first large scale application has been realized. This paper describes the different components of the workstation environment for the implementation of the applications. The focus is on the set of tools which have been used, developed or integrated, and on how we plan to make them evolve. (author)

  3. Status of the anti-proton production beam in the CERN PS

    International Nuclear Information System (INIS)

    Cappi, R.; Evans, B.J.; Garoby, R.

    1990-01-01

    A new scheme was put into operation in November 1988 to upgrade the proton beam delivered by the 26 GeV Proton Synchrotron (PS) for anti-proton production. It makes use of quasi-adiabatic manipulations of the RF parameters to squeeze a beam filling 1/2 of the PS circumference into a 1/4 turn and can in theory preserve the longitudinal emittance. A maximum intensity of 1.68 e 13 ppp in 5 bunches at 26 GeV has been reached in the course of 22 weeks of operation. The limitations of the performance are analysed together with possible improvements. (author) 6 refs., 9 figs

  4. Distributed memory in a heterogeneous network, as used in the CERN-PS complex timing system

    CERN Document Server

    Kovaltsov, V I

    1995-01-01

    The Distributed Table Manager (DTM) is a fast and efficient utility for distributing named binary data structures called Tables, of arbitrary size and structure, around a heterogeneous network of computers to a set of registered clients. The Tables are transmitted over a UDP network between DTM servers in network format, where the servers perform the conversions to and from host format for local clients. The servers provide clients with synchronization mechanisms, a choice of network data flows, and table options such as keeping table disc copies, shared memory or heap memory table allocation, table read/write permissions, and table subnet broadcasting. DTM has been designed to be easily maintainable, and to automatically recover from the type of errors typically encountered in a large control system network. The DTM system is based on a three level server daemon hierarchy, in which an inter daemon protocol handles network failures, and incorporates recovery procedures which will guarantee table consistency w...

  5. The Low-Level Control System for the CERN PS Multi-Turn Extraction Kickers

    CERN Document Server

    Schipper, J; Boucly, C; Carlier, E; Fowler, T; Gaudillet, H; Noulibos, R; Sermeus, L

    2010-01-01

    To reduce the beam losses when preparing high intensity proton beam for the CERN Neutrino to Gran Sasso (CNGS) facility, a new Multi-Turn extraction (MTE) scheme has been implemented in the PS, to replace the present Continuous Transfer (CT) to the SPS. Industrial off-the-shelf components have been used for the low-level part of the MTE kicker control system. National Instruments PXI systems are used to control the high voltage pulse generators and a SIEMENS programmable logic controller (PLC) handles the centralised oil cooling and gas insulation sub-systems

  6. Septum magnet MNP-23 for the CERN PS experimental area and its fast interlock system

    CERN Document Server

    Borburgh, J; Prost, A; Zickler, T

    2004-01-01

    Two MNP-23 septum-like magnets are installed at CERN in the transfer line from the Proton Synchrotron (PS) to the East Hall Experimental Area. They are exposed to extremely high doses of ionizing radiation. In the past, the magnets experienced two catastrophic failures due to overheating of its coils and cannot be repaired. The magnets of improved design which is subject of this article are built as replacements for the magnets presently installed. The MNP-23 is a resistive C shaped iron-dominated magnet made of solid low carbon steel blocks. The excitation windings consist of two water-cooled coils wound from hollow copper conductor. The septum design of these magnets implies a high current density which requires an efficient water cooling system. The newly designed cooling circuit provides better cooling performance and more reliability. To avoid failures due to coil overheating, an elaborate interlock system was developed and installed. It consists of two parts: firstly a slow, more classic sensor, to dete...

  7. CERN PS Optical Properties Measured with Turn-By-Turn Orbit Data

    CERN Document Server

    Bach, T; Giovannozzi, M; Hernalsteens, C; Lachaize, A; Sterbini, G; Tom´as, R; Wasef, R

    2013-01-01

    The performance of the CERN Proton Synchrotron (PS) has been constantly increasing over the years both in terms of beam parameters (intensity and brightness) and beam manipulations (transverse and longitudinal splitting). This implies a very good knowledge of the linear and non-linear model of the ring. In this paper we report on a detailed campaign of beam measurements based on turn-by-turn orbit data aimed at measuring the optics in several conditions as well as the resonance driving terms.

  8. Multiturn Extraction Based on Trapping in Stable Islands at CERN PS: Recent Measurement Advances

    CERN Multimedia

    Cappi, R; Giovannozzi, Massimo; Martini, M; Métral, Elias; Müller, A S; Sakumi, A; Steerenberg, R

    2004-01-01

    Recently a novel approach to perform multi-turn extraction was proposed based on beam splitting in the transverse phase space by means of trapping inside stable islands. During the year 2002, preliminary measurements at the CERN Proton Synchrotron with a low-intensity, singlebunch, proton beam, confirmed the possibility of generating various beamlets starting from a single Gaussian beam. The experimental campaign continued also during the year 2003 to assess a number of key issues, such as the feasibility of trapping with high-intensity beam and capture efficiency. The experimental results are presented and discussed in detail in this paper.

  9. Power generation from a 7700C heat source by means of a main steam cycle, a topping closed gas cycle and a ammonia bottoming cycle

    International Nuclear Information System (INIS)

    Tilliette, Z.P.

    1981-03-01

    For power generation, steam cycles make an efficient use of medium temperature heat sources. They can be adapted to dry cooling, higher power ratings and output increase in winter by addition of an ammonia bottoming cycle. Active development is carried out in this field by 'Electricite de France'. As far as heat sources at higher temperatures are concerned, particularly related to coal-fired or nuclear power plants, a more efficient way of converting energy is at first to expand a hot working fluid through a gas turbine. It is shown in this paper that a satisfactory result, for heat sources of about 770 0 C, is obtained with a topping closed gas cycle of moderate power rating, rejecting its waste heat into the main steam cycle. Attention has to be paid to this gas cycle waste heat recovery and to the coupling of the gas and steam cycles. This concept drastically reduces the importance of new technology components. The use and the significance of an ammonia bottoming cycle in this case are investigated

  10. Noise annoyances from wind power: Survey of the population living close to a wind power plant. Final report: Part 3 Main study

    International Nuclear Information System (INIS)

    Pedersen, Eja; Persson-Waye, K.

    2002-02-01

    To evaluate the occurrence of annoyance from wind turbines, a study was performed in Laholm in May 2000. The aim was to obtain dose response relationships between calculated sound levels and noise annoyance and appropriate sound description as well as analysing the influence of other variables on noise annoyance. A questionnaire survey was performed in 6 areas comprising 16 wind turbines, of which 14 had an effect of 600 kW. The purpose of the study was masked. Among questions on living conditions in the countryside, questions directly related to wind turbines were included. The study population (n=518) comprised one randomly selected subject between the ages of 18 to 75 years in each household living within a calculated wind turbine sound level of 25 to 40 dBA. The response rate was 68.7% (n=356). Calculated distributions of A-weighted sound level were performed for each area and plotted on geographical maps in 2.5 dBA steps. Each dwelling could thus be given a sound level within an interval of 2.5 dBA. The most frequently occurring source of noise annoyance was noise from rotor blades. The proportions of respondents annoyed by noise increased with calculated sound level. Among respondents exposed to sound levels of 35.0-37.5 dBA, 43% responded themselves to be rather or much annoyed. A-weighted sound level was only one variable explaining annoyance. Annoyance was correlated to a larger extent by the intrusiveness of the sound character swishing. Noise annoyance was interrelated to the respondents' opinion of the visual impact of wind turbines, while attitude towards wind power in general had no greater influence. Disturbance of spoilt view was reported to a similar degree as noise disturbance. Further investigations are needed to clarify factors of importance for the disturbance of view. All the wind turbines in the study had constant rotation speed. The greater wind turbines that are now erected often have variable speed, which may lead to a sound comprising

  11. From mains frequency to converter power supply in foundry melting operations; Von der Netzfrequenz- zur Umrichter-Stromversorgung im Schmelzbetrieb der Eisengiesserei

    Energy Technology Data Exchange (ETDEWEB)

    Doetsch, Erwin; Yildir, Yilmaz [ABP Induction Systems GmbH, Dortmund (Germany); Koch, Frank [Gusstec Weiherhammer GmbH, Weiherhammer (Germany)

    2010-06-15

    As is well known, converter-based power feed has now largely superseded line-frequency technology as state-of-the-art in supply of induction melting facilities. Replacement of LF power supply systems with converters is therefore the main priority in the context of projects for modernization of existing induction installations. The objective is generally to leave the crucible furnace and its peripherals effectively as they are, and match the output and frequency of the converter to their needs. The following article states the criteria that need to be taken into account in this context and examines a specific modernization project, using the example of Gusstec Weiherhammer GmbH's iron melting installation. (orig.)

  12. Shaking table test of a base isolated model in main control room of nuclear power plant using LRB (lead rubber bearing)

    International Nuclear Information System (INIS)

    Ham, K. W.; Lee, K. J.; Suh, Y. P.

    2005-01-01

    LRB(Lead Rubber Bearing) is a widely used isolation system which is installed between equipment and foundation to reduce seismic vibration from ground. LRB is consist of bearings which are resistant to lateral motion and torsion and has a high vertical stiffness. For that reason, several studies are conducted to apply LRB to the nuclear power plant. In this study, we designed two types of main control floor systems (type I, type II) and a number of shaking table tests with and without isolation system were conducted to evaluate floor isolation effectiveness of LRB

  13. Technical evaluation report on the seven main transformer failures at the North Anna Power Station, Units 1 and 2 (Docket Nos. 50-338, 50-339)

    International Nuclear Information System (INIS)

    Dalton, K.J.; Kresser, J.V.; Savage, J.W.; Selan, J.C.

    1984-01-01

    This report documents technical evaluations on various aspects pertaining to the seven main transformer failures at the North Anna Power Station, Units 1 and 2. These reports cover the subjects of Probability Risk Assessment (PRA), Failure Modes and Effects Analysis (FMEA), Root Causes, Protection Systems, Modifications, Failure Statistics, and Generic Aspects. The PRA determined that the contribution from a main transformer failure affecting plant safety systems so as to increase the risk to the public health and safety is negligible. The FMEA determined that a main transformer failure can have primary and secondary effects on plant safety system operation. The evaluation of the Root Causes found that no single common cause contributed to the seven failures. Each failure was found to have specific circumstances for initiating the failure. Both the generator and transformer primary protection systems were found to perform correctly and were designed within industry standards and practices. The proposed modifications resulting from the analyses of the failures will improve system reliability and integrity, and will reduce potentially damaging effects. The failure statistic survey found very limited data bases from which a meaningful correlation could be ascertained. The statistical comparison found no appreciable anomalies with the NAPS failures. The evaluation of all the available information and the results of the separate reports on the main transformer failures found that several generic concerns exist

  14. Site preparation and excavation works for the foundation of station main building among construction works for No. 1 unit in Kashiwazaki-Kariwa Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Ueyama, Koreyasu [Tokyo Electric Power Co., Inc. (Japan)

    1982-09-01

    Tokyo Electric Power Co., Inc., is planning the nuclear power station of final capacity 8,000 MW (7 units) in the region spread over Kashiwazaki City and Kariwa Village in Niigata Prefecture. For No. 1 unit (1100 MWe BWR), the reactor installation license was obtained in September, 1977, the site preparation and road construction started in April, 1978, and harbour construction works started in August, 1979. The construction works are now at the peak, and the overall progressing rate as of the end of June, 1982, is about 51 %. The site is a hilly region of dune along the coast of the Sea of Japan, and No. 1 unit is located in the southern part of the site. This paper reports on the outline of the project, site preparation and excavation works for the foundation of the station main building. For the site preparation and the excavation works for the foundation the main building, the shape of slope cutting, the design of landslide-preventing wall for the vertical excavation for the reactor complex building, and the construction plan and the result are reported. For underground water impermeable wall works, its outline, groundwater condition, groundwater simulation analysis, the investigation of wall installation, the wall structure and construction are described in detail. Also the outline of the control of slope face measurement, the control standards and the measured results are reported.

  15. A coupled 3-D kinetics/system thermal-hydraulic analysis of main steam line break accident for Optimized Power Reactor 1000

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Yung Kwon; Choi, Chul Jin; Kim, Eun Kee; Lee, Sang Yong [Korea Power Engineering Company, Inc, 150 Deokjin-dong, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2006-07-01

    This paper presents the results of the coupled 3-D neutronics/thermal-hydraulic analysis of hypothetical main steam line break (MSLB) accident for Optimized Power Reactor 1000. One of the major concerns of this accident is a return-to-power occurrence accompanied with extremely large radial peaking near the stuck Control Element Assembly (CEA). The conventional point kinetics application does not properly account for this kind of asymmetric and local core behavior. Therefore, the current licensing method of point kinetics application introduces some uncertainties and conservatisms in the physics parameters generation, e.g., the static net scram rod worth, moderator cooldown reactivity, Doppler reactivity, and a 3-D peaking factor. The recently developed UNICORN-TM code system is applied for the 3-D coupled calculation, where neutronics code MASTER is coupled with the best-estimate system transient code RETRAN. The 3-D coupled results were assessed in comparison with those by point kinetics application using stand-alone RETRAN application. To quantify the 3-D reactivity benefits over point kinetics, both calculations assumed the accidents to be initiated from the same core state, e.g., end of cycle burnup, fuel and CEA configuration with the same initial moderator and Doppler temperature coefficient, and with initial system thermal-hydraulic condition. The core physics parameters required for point kinetics application were produced using MASTER with the method and procedure consistent with the current licensing application. The occurrence of return-to-power was simulated by intentionally reducing the net CEA worth in order to assess the spatial power distribution and local T-H effect on the dynamic reactivity feedback. The results have demonstrated that the 3-D analysis removes some of the conservatisms inherent in point kinetics analysis mainly caused by the inability to properly account for local reactivity feedback effects during return-to-power transient

  16. A coupled 3-D kinetics/system thermal-hydraulic analysis of main steam line break accident for Optimized Power Reactor 1000

    International Nuclear Information System (INIS)

    Jin, Yung Kwon; Choi, Chul Jin; Kim, Eun Kee; Lee, Sang Yong

    2006-01-01

    This paper presents the results of the coupled 3-D neutronics/thermal-hydraulic analysis of hypothetical main steam line break (MSLB) accident for Optimized Power Reactor 1000. One of the major concerns of this accident is a return-to-power occurrence accompanied with extremely large radial peaking near the stuck Control Element Assembly (CEA). The conventional point kinetics application does not properly account for this kind of asymmetric and local core behavior. Therefore, the current licensing method of point kinetics application introduces some uncertainties and conservatisms in the physics parameters generation, e.g., the static net scram rod worth, moderator cooldown reactivity, Doppler reactivity, and a 3-D peaking factor. The recently developed UNICORN-TM code system is applied for the 3-D coupled calculation, where neutronics code MASTER is coupled with the best-estimate system transient code RETRAN. The 3-D coupled results were assessed in comparison with those by point kinetics application using stand-alone RETRAN application. To quantify the 3-D reactivity benefits over point kinetics, both calculations assumed the accidents to be initiated from the same core state, e.g., end of cycle burnup, fuel and CEA configuration with the same initial moderator and Doppler temperature coefficient, and with initial system thermal-hydraulic condition. The core physics parameters required for point kinetics application were produced using MASTER with the method and procedure consistent with the current licensing application. The occurrence of return-to-power was simulated by intentionally reducing the net CEA worth in order to assess the spatial power distribution and local T-H effect on the dynamic reactivity feedback. The results have demonstrated that the 3-D analysis removes some of the conservatisms inherent in point kinetics analysis mainly caused by the inability to properly account for local reactivity feedback effects during return-to-power transient

  17. Participation of the national industry within a nuclear power plant program by technology transfer from the point of view of the main contractor

    International Nuclear Information System (INIS)

    Kopp, H.

    1986-04-01

    The broad scope of components needed in a nuclear power plant with various technical requirements offer a big opportunity for the participation of local industries in the construction of such plants. Depending on the existing capability of the industrial enterprises, the scope of national participation can be increased by technology transfer on all technical areas to be applied for the construction of NPPs. Such technology requires as basis a nuclear program of the country determined and supported by the government and the utilities. This program has to be defined as realistic as even possible adjoined to the future energy demand of the country. Furthermore the available capability, existing qualifications and equipment of the national industry have to be considered. On the basis of these fundamental requirements a tailormade technology transfer program has to be elaborated in close cooperation with an experienced main contractor of the plant and his partners for such technology transfer and should be established afterwards. This program has to consider not only the goal to achieve finally the independent production of components and equipment for NPPs or the construction of complete power plant units itself, but also the economic benefit of such a program for the country. The costs of technology transfer and the necessary investment of the national industry required for the manufacture of nuclear components have to be thoroughly investigated, based on the expected scope of products to be manufactured for the nuclear power plants according to the nuclear program. Furthermore the application of the technology transferred for other components e.g. for conventional power stations, mineral-oil or chemical industrial plants has to be considered. By a tailormade nuclear technology transfer program, executed by qualified and experienced partners not only the quality of the products of the national industry for NPPs will be improved, but also the general standard regarding

  18. Main Memory

    NARCIS (Netherlands)

    P.A. Boncz (Peter); L. Liu (Lei); M. Tamer Özsu

    2008-01-01

    htmlabstractPrimary storage, presently known as main memory, is the largest memory directly accessible to the CPU in the prevalent Von Neumann model and stores both data and instructions (program code). The CPU continuously reads instructions stored there and executes them. It is also called Random

  19. Integration of biomass into urban energy systems for heat and power. Part II: Sensitivity assessment of main techno-economic factors

    International Nuclear Information System (INIS)

    Pantaleo, Antonio M.; Giarola, Sara; Bauen, Ausilio; Shah, Nilay

    2014-01-01

    Highlights: • Application of a MILP tool for optimal sizing and location of heating and CHP plants to serve residential energy demand. • Trade-offs between local vs centralized heat generation, district heating vs natural gas distribution systems. • Assessment of the key factors influencing the use of biomass and district heating in residential areas. - Abstract: The paper presents the application of a mixed integer linear programming (MILP) methodology to optimize multi-biomass and natural gas supply chain strategic design for heat and power generation in urban areas. The focus is on spatial and temporal allocation of biomass supply, storage, processing, transport and energy conversion (heat and CHP) to match the heat demand of residential end users. The main aim lies on the assessment of the trade-offs between centralized district heating plants and local heat generation systems, and on the decoupling of the biomass processing and biofuel energy conversion steps. After a brief description of the methodology, which is presented in detail in Part I of the research, an application to a generic urban area is proposed. Moreover, the influence of energy demand typologies (urban areas energy density, heat consumption patterns, buildings energy efficiency levels, baseline energy costs and available infrastructures) and specific constraints of urban areas (transport logistics, air emission levels, space availability) on the selection of optimal bioenergy pathways for heat and power is assessed, by means of sensitivity analysis. On the basis of these results, broad considerations about the key factors influencing the use of bioenergy into urban energy systems are proposed. Potential further applications of this model are also described, together with main barriers for development of bioenergy routes for urban areas

  20. Function generation and regulation libraries and their application to the control of the new main power converter (POPS) at the CERN CPS

    International Nuclear Information System (INIS)

    King, Q.; Page, S.T.; Thiesen, H.; Veenstra, M.

    2012-01-01

    Power converter control for the LHC is based on an embedded control computer called a Function Generator/Controller (FGC). Every converter includes an FGC with responsibility for the generation of the reference current as a function of time and the regulation of the circuit current, as well as control of the converter state. With many new converter controls software classes in development it was decided to generalize several key components of the FGC software in the form of C libraries: function generation in libfg, regulation, limits and simulation in libreg and DCCT, ADC and DAC calibration in libcal. These libraries were first used in the software class dedicated to controlling the new 60 MW main power converter (POPS) at the CERN Proton Synchrotron (CPS) where regulation of both magnetic field and circuit current is supported. This paper reports on the functionality provided by each library and in particular libfg and libreg. The libraries are already being used by software classes in development for the next generation FGC for Linac4 converters, as well as the CERN SPS converter controls (MUGEF) and MedAustron converter regulation board. (authors)

  1. Main Memory

    OpenAIRE

    Boncz, Peter; Liu, Lei; Özsu, M.

    2008-01-01

    htmlabstractPrimary storage, presently known as main memory, is the largest memory directly accessible to the CPU in the prevalent Von Neumann model and stores both data and instructions (program code). The CPU continuously reads instructions stored there and executes them. It is also called Random Access Memory (RAM), to indicate that load/store instructions can access data at any location at the same cost, is usually implemented using DRAM chips, which are connected to the CPU and other per...

  2. IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    that digital technology offers are needed to increase cost-effective electricity production. As an integral part of the I and C modernization program at a nuclear power plant, the control room and other human-system interfaces (HSIs) will also be modernized. To support safe and effective operation, it is critical to specify, design, implement, operate, and maintain, as well as train for, the control room and HSI changes to take advantage of human cognitive processing abilities. This consideration of human factors is essential to increase performance and to reduce the likelihood of human errors. The plant I and C and HSI modifications can affect personnel in various ways. They can impact the role of personnel, the tasks to be performed, the way tasks are performed, and the knowledge, skills and training required of personnel. As part of modernization, HSIs are becoming more computer-based, incorporating features such as soft controls and computerized procedures, touch-screen interfaces, sit-down workstations, and large-screen overview displays. As computer-based technologies are integrated into control rooms that were largely based on conventional technology, hybrid control rooms are created. The potential benefits of implementing digital technology include more efficient operations and maintenance, leading to improved power plant availability and safety through the avoidance of transients, forced outages, and unnecessary shutdowns. The potential benefits also include increased efficiency and power output as well as reduced operating costs. New digital systems provide the opportunity to give personnel information they did not have with conventional systems. The importance of these issues has led the IAEA to organize (in conjunction with AECL) an international forum for presentations and discussions on the potential benefits and challenges related to the integration of Analog and Digital Instrumentation and Control Systems in Hybrid Main Control Rooms. Many of these

  3. Analysis of the main steam line break accident with loss of offsite power using the fully coupled RELAP5/PANTHER/COBRA code package

    International Nuclear Information System (INIS)

    Ruben Van Parys; Sandrine Bosso; Christophe Schneidesch; Jinzhao Zhang

    2005-01-01

    Full text of publication follows: A coupled thermal hydraulics-neutronics code package (RELAP5/PANTHER/COBRA) has been qualified for accident analysis at Tractebel Engineering. In the TE coupled code package, the best estimate thermal-hydraulic system code, RELAP5/MOD2.5, is coupled with the full three-dimensional reactor core kinetics code, PANTHER, via a dynamic data exchange control and processing tool, TALINK. An interface between PANTHER code and the sub-channel thermal-hydraulic analysis code COBRA-IIIC is developed in order to perform online calculation of Departure from Nucleate Boiling Ratio (DNBR). The TE coupled code package has been applied to develop a MSLB accident analysis methodology using the TE deterministic bounding approach. The methodology has been applied for MSLB accident analysis in support of licensing of the power up-rate and steam generator replacement of the Doel 2 plant. The results of coupled thermal-hydraulic and neutronic analysis of SLB show that there exists an important margin in the traditional FSAR MSLB accident analysis. As a specific licensing requirement, the main steam line break accident with loss of offsite power has to be analyzed. In the standard methodology with the coupled RELAP5/PANTHER code, and some corrective methods has to be taken in order to overcome the limitations due to the close-channel T/H model in PANTHER at low flow conditions. The results show that the steam line break accident with loss of offsite power is far less limiting. In order to verify the effect of the cross-flow at low flow conditions, the fully dynamic coupling of RELAP5/PANTHER/COBRA code package is used for reanalysis of this case, in which the PANTHER close-channel T/H model is replaced by the COBRA sub-channel T/H model with crossflow option. It has been demonstrated that, although the consideration of cross-flow in this challenging situation may lead to higher core return to power and slightly lower DNBR than in the standard methodology

  4. Analysis of the main steam line break accident with loss of offsite power using the fully coupled RELAP5/PANTHER/COBRA code package

    Energy Technology Data Exchange (ETDEWEB)

    Ruben Van Parys; Sandrine Bosso; Christophe Schneidesch; Jinzhao Zhang [Nuclear Department, Suez-Tractebel Engineering, avenue Ariane 5, B-1200 Brussels (Belgium)

    2005-07-01

    Full text of publication follows: A coupled thermal hydraulics-neutronics code package (RELAP5/PANTHER/COBRA) has been qualified for accident analysis at Tractebel Engineering. In the TE coupled code package, the best estimate thermal-hydraulic system code, RELAP5/MOD2.5, is coupled with the full three-dimensional reactor core kinetics code, PANTHER, via a dynamic data exchange control and processing tool, TALINK. An interface between PANTHER code and the sub-channel thermal-hydraulic analysis code COBRA-IIIC is developed in order to perform online calculation of Departure from Nucleate Boiling Ratio (DNBR). The TE coupled code package has been applied to develop a MSLB accident analysis methodology using the TE deterministic bounding approach. The methodology has been applied for MSLB accident analysis in support of licensing of the power up-rate and steam generator replacement of the Doel 2 plant. The results of coupled thermal-hydraulic and neutronic analysis of SLB show that there exists an important margin in the traditional FSAR MSLB accident analysis. As a specific licensing requirement, the main steam line break accident with loss of offsite power has to be analyzed. In the standard methodology with the coupled RELAP5/PANTHER code, and some corrective methods has to be taken in order to overcome the limitations due to the close-channel T/H model in PANTHER at low flow conditions. The results show that the steam line break accident with loss of offsite power is far less limiting. In order to verify the effect of the cross-flow at low flow conditions, the fully dynamic coupling of RELAP5/PANTHER/COBRA code package is used for reanalysis of this case, in which the PANTHER close-channel T/H model is replaced by the COBRA sub-channel T/H model with crossflow option. It has been demonstrated that, although the consideration of cross-flow in this challenging situation may lead to higher core return to power and slightly lower DNBR than in the standard methodology

  5. The development of software and formation of a database on the main sources of environmental contamination in areas around nuclear power plants

    International Nuclear Information System (INIS)

    Palitskaya, T.A.; Novikov, A.V.; Makeicheva, M.A.; Ivanov, E.A.

    2004-01-01

    Providing of environmental safety control in the process of nuclear power plants (NPPs) operation, environmental protection and rational use of the natural resources is one of the most important tasks of the Rosenergoatom Concern. To ensure the environmental safety, trustworthy, complete and timely information is needed on the natural resources availability and condition, on the natural environment quality and its contamination level. The industrial environmental monitoring allows obtaining, processing and evaluating data for making environmentally acceptable and economically efficient decisions. The industrial environmental monitoring system at NPPs is formed taking into account both radiation and non-radiation factors of impact. Obtaining data on non-radiation factors of the NPP impact is provide by a complex of special observations carried out by NPP's environment protection services. The gained information is transmitted to the Rosenergoatom Concern and input to a database of the Environment Protection Division of the Concern Department of Radiation Safety, Environment Protection and Nuclear Materials Accounting. The database on the main sources of environmental contamination in the areas around NPPs will provide the high level of the environmental control authenticity, maintenance of the set standards, and also - automation of the most labor-consuming and frequently repeating types of operations. he applied software is being developed by specialists from the All-Russia Research Institute of Nuclear Power Plants on the basis of the database management system Microsoft SQL Server using VBA and Microsoft Access. The data will be transmitted through open communication channels. The geo-referenced digital mapping information, basing on the ArcGIS and MapInfo will be the main forms of output data presentation. The Federal authority bodies, their regional units and the Concern's sub-divisions involved in the environmental protection activities will be the database

  6. The development of software and formation of a database on the main sources of environmental contamination in areas around nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Palitskaya, T.A.; Novikov, A.V. [Rosenergoatom Concern, Moscow (Russian Federation); Makeicheva, M.A.; Ivanov, E.A. [All-Russia Research Institute of Nuclear Power Plants, Moscow (Russian Federation)

    2004-07-01

    Providing of environmental safety control in the process of nuclear power plants (NPPs) operation, environmental protection and rational use of the natural resources is one of the most important tasks of the Rosenergoatom Concern. To ensure the environmental safety, trustworthy, complete and timely information is needed on the natural resources availability and condition, on the natural environment quality and its contamination level. The industrial environmental monitoring allows obtaining, processing and evaluating data for making environmentally acceptable and economically efficient decisions. The industrial environmental monitoring system at NPPs is formed taking into account both radiation and non-radiation factors of impact. Obtaining data on non-radiation factors of the NPP impact is provide by a complex of special observations carried out by NPP's environment protection services. The gained information is transmitted to the Rosenergoatom Concern and input to a database of the Environment Protection Division of the Concern Department of Radiation Safety, Environment Protection and Nuclear Materials Accounting. The database on the main sources of environmental contamination in the areas around NPPs will provide the high level of the environmental control authenticity, maintenance of the set standards, and also - automation of the most labor-consuming and frequently repeating types of operations. he applied software is being developed by specialists from the All-Russia Research Institute of Nuclear Power Plants on the basis of the database management system Microsoft SQL Server using VBA and Microsoft Access. The data will be transmitted through open communication channels. The geo-referenced digital mapping information, basing on the ArcGIS and MapInfo will be the main forms of output data presentation. The Federal authority bodies, their regional units and the Concern's sub-divisions involved in the environmental protection activities will be the

  7. A Development Method of Mobile Computerized Procedure System for the Cooperation among Field Workers and Main Control Room Operators in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Sun Jin; Seong, No Kyu; Jung, Yeon Sub

    2014-01-01

    Human errors can occur during the test and maintenance of steam generator, safety injection system and other various systems and devices in nuclear power plants (NPPs). Most of human errors can be improved by the human error prevention techniques such as self-check, peer-check, concurrent verification and etc. Another important technique is to share work information among main control room (MCR) operators and field workers. Various field service automation tools have been developed with recent information technology in many countries. APR1400 computerized procedure system (CPS) has been developed for the MCR operators of Shin-Kori 3 and 4 units. Especially, the concurrent verification support design is applied in the construction project of Shin-Hanul 1 and 2 CPS. It is expected that the proposed mobile CPS can enhance the reduction of human errors by supporting human error prevention techniques and information sharing. This paper describes the technical issues of the mobile CPS (mobile CPS) in the initial development stage. Based on the design of APR1400, CRI CPS has been developed and operated for SKN 3 and 4 HFE V and V and license test for the MCR operating staff. Therefore the mobile CPS will be developed by upgrading the CRI CPS with improved features

  8. A Development Method of Mobile Computerized Procedure System for the Cooperation among Field Workers and Main Control Room Operators in Korean Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sun Jin; Seong, No Kyu; Jung, Yeon Sub [KHNP ,Daejeon (Korea, Republic of)

    2014-08-15

    Human errors can occur during the test and maintenance of steam generator, safety injection system and other various systems and devices in nuclear power plants (NPPs). Most of human errors can be improved by the human error prevention techniques such as self-check, peer-check, concurrent verification and etc. Another important technique is to share work information among main control room (MCR) operators and field workers. Various field service automation tools have been developed with recent information technology in many countries. APR1400 computerized procedure system (CPS) has been developed for the MCR operators of Shin-Kori 3 and 4 units. Especially, the concurrent verification support design is applied in the construction project of Shin-Hanul 1 and 2 CPS. It is expected that the proposed mobile CPS can enhance the reduction of human errors by supporting human error prevention techniques and information sharing. This paper describes the technical issues of the mobile CPS (mobile CPS) in the initial development stage. Based on the design of APR1400, CRI CPS has been developed and operated for SKN 3 and 4 HFE V and V and license test for the MCR operating staff. Therefore the mobile CPS will be developed by upgrading the CRI CPS with improved features.

  9. On results of measurement and method of behavior analysis for land slide protection wall in excavation works for main building foundation of No.2 plant in Kashiwazaki-Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Otsuki, Hideo; Tsuchi, Hiroyuki; Nishioka, Toshimichi

    1987-01-01

    Tokyo Electric Power Co. has been constructing the nuclear power station having 8 million kW capacity of seven BWR plants in the site of about 4.2 million m 2 in Niigata Prefecture. No.1 BWR plant of 1100 MWe output started the operation in September, 1985. As a rule, the important structures in nuclear power stations such as a reactor building and a turbine building are to be directly supported on bedrocks, and in this case, on the mudstone of Nishiyama strata. As this Nishiyama strata exists in large depth, the excavation works for the foundations of buildings are to be carried out by installing large scale land slide protection walls. In this report, among the excavation works for the main building foundation of No.2 plant, the results of examining the behavior of the land slide protection wall installed in soft rock ground based on the results of measurement of vertical excavation by land slide protection method and the techniques of its analysis are described. The geological features, the design of land slide protection walls, the measurement of the land slide protection walls and surrounding ground and the results, and the examination of the analysis methods by a beam model and FEM are reported. (Kako, I.)

  10. Main findings

    International Nuclear Information System (INIS)

    2014-01-01

    Licensing regimes vary from country to country. When the license regime involves several regulators and several licenses, this may lead to complex situations. Identifying a leading organisation in charge of overall coordination including preparation of the licensing decision is a useful practice. Also, if a stepwise licensing process is implemented, it is important to fix in legislation decisions and/or time points and to identify the relevant actors. There is considerable experience in civil and mining engineering that can be applied when constructing a deep geological disposal facility. Specific challenges are, however, the minimization of disturbances to the host rock and the understanding of its long-term behavior. Construction activities may affect the geo-hydraulic and geochemical properties of the various system components which are important safety features of the repository system. Clearly defined technical specifications and an effective quality management plan are important in ensuring successful repository implementation which is consistent with safety requirements. Monitoring plan should also be defined in advance. The regulatory organization should prepare itself to the licensing review before construction by allocating sufficient resources. It should increase its competence, e.g., by interacting early with the implementer and through its own R and D. This will allow the regulator to define appropriate technical conditions associated to the construction license and to elaborate a relevant inspection plan of the construction work. After construction, obtaining the operational license is the most important and crucial step. Main challenges include (a) establishing sufficient confidence so that the methods for closing the individual disposal units comply with the safety objectives and (b) addressing the issue of ageing of materials during a 50-100 years operational period. This latter challenge is amplified when reversibility/retrievability is required

  11. Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Min, E-mail: jewellee@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Lee, Hyun Chul, E-mail: leehc@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Ha, Jun Su, E-mail: junsu.ha@kustar.ac.ae [Department of Nuclear Engineering, Khalifa University of Science Technology and Research, Abu Dhabi P.O. Box 127788 (United Arab Emirates); Seong, Poong Hyun, E-mail: phseong@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

    2016-10-15

    Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

  12. Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Seung Min; Lee, Hyun Chul; Ha, Jun Su; Seong, Poong Hyun

    2016-01-01

    Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

  13. Independent power source hybrid system - recent examples mainly of mountain huts.; Dokuritsu dengengata no haiburiddo shisutemu -saikin no yamagoya deno jirei wo chushin ni.

    Energy Technology Data Exchange (ETDEWEB)

    Mori, T. [Kanagawa Inst. of Tech., Kanagawa (Japan)

    2000-09-30

    History of the independent power source hybrid systems used at such as mountain huts were outlined, and recent application examples of the hybrid systems were explained. At Natsuzawa mineral spring in Nagano pref., 7 kW of hybrid power generator system composed of solar cell and wind power generator, as well as 400 W of small hydraulic power generator are working supplying electric power for the private sewerage system, and the system without diesel generator is being tested. At Senjogahara refuge hut in South Alps, a hybrid power generation system composed of 10.7 kW of solar cell and 6.4 kW of wind power generator was installed, and is working. In mountainous area, there exist critical factors such as weather condition and difficulty in carrying equipment, accordingly, cost reduction and sizing down of relevant apparatus such as batteries and inverters are expected. (NEDO)

  14. The study of the dynamics of migration main radiologically significant isotopes in the near and far field Chernobyl nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Bondarkov, M.; Bondarkov, D.; Maksymenko, A. [Chornobyl Center for Nuclear Safety, Radioactive Waste and Radioecology (Ukraine); Zheltonozhskaya, M.; Zheltonozhsky, V. [Institute for nuclear research (Ukraine)

    2014-07-01

    The study of the migration of {sup 90}Sr, {sup 137}Cs, {sup 241}Am and Pu isotopes in soil near Chernobyl nuclear power plant area, as well as the Chernigov region, Ukraine is described. Experiments were conducted using a semiconductor spectrometry and radiochemical separation of isotopes needed. The experimental data obtained were processed using a mathematical model that takes into account in convective component (fit parameter V-- linear velocity of radionuclide movement dependent upon soil moisture) and diffusive one (fit parameter D- diffusion coefficient) migration of isotopes. The parameter values in V and D of migration, in turn, allow us to estimate halftime of decontamination top five-centimeter layer of soil. The results obtained in this paper halftime of decontamination for the various isotopes and their comparison with those obtained by us and by other authors in the past 10-20 years, confirms the trend previously noticed by a significant speeding migration Radiostrontium compared with Radiocesium. It is shown that for all the types studied soils in the late phase of Chernobyl accident halftime of decontamination of the top 5 - cm soil layer for radiostrontium, and for radioactive cesium in the order of magnitude or more greater than the period of the physical half-life of the radionuclide that is, matching in the late phase of the accident change the exposure dose of radiation is mainly determined by the physical decay of the radionuclide. According to the estimated periods decontamination upper soil horizons of different migration mobility of radionuclides in soils exclusion zone reduced in number: {sup 90}Sr> {sup 137}Cs> {sup 241}Am ≥ {sup 238-240}Pu, migration mobility of isotopes of transuranic elements is very low. Document available in abstract form only. (authors)

  15. Main facts 1995

    International Nuclear Information System (INIS)

    1996-01-01

    This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: new applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, monitoring and plants operations

  16. Main facts 1993

    International Nuclear Information System (INIS)

    1994-01-01

    This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: new applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, network analysis, information and informatic equipment

  17. Survey of strong motion earthquake effects on thermal power plants in California with emphasis on piping systems. Volume 1, Main report

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1995-11-01

    Since 1982, there has been a major effort expended to evaluate the susceptibility of nuclear Power plant equipment to failure and significant damage during seismic events. This was done by making use of data on the performance of electrical and mechanical equipment in conventional power plants and other similar industrial facilities during strong motion earthquakes. This report is intended as an extension of the seismic experience data collection effort and a compilation of experience data specific to power plant piping and supports designed and constructed US power piping code requirements which have experienced strong motion earthquakes. Eight damaging (Richter Magnitude 7.7 to 5.5) California earthquakes and their effects on 8 power generating facilities in use natural gas and California were reviewed. All of these facilities were visited and evaluated. Seven fossel-fueled (dual use natural gas and oil) and one nuclear fueled plants consisting of a total of 36 individual boiler or reactor units were investigated. Peak horizontal ground accelerations that either had been recorded on site at these facilities or were considered applicable to these power plants on the basis of nearby recordings ranged between 0.20g and 0.5lg with strong motion durations which varied from 3.5 to 15 seconds. Most US nuclear power plants are designed for a safe shutdown earthquake peak ground acceleration equal to 0.20g or less with strong motion durations which vary from 10 to 15 seconds

  18. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  19. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks.

  20. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE

  1. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

  2. Implications of the accident at Chernobyl for safety regulation of commercial nuclear power plants in the United States: Volume 1, Main report: Final report

    International Nuclear Information System (INIS)

    1989-04-01

    This report was prepared by the Nuclear Regulatory Commission (NRC) staff to assess the implications of the accident at the Chernobyl nuclear power plant as they relate to reactor safety regulation for commercial nuclear power plants in the United States. The facts used in this assessment have been drawn from the US fact-finding report (NUREG-1250) and its sources. The general conclusions of the document are that there are generic lessons to be learned but that no changes in regulations are needed due to the substantial differences in the design, safety features and operation of US plants as compared to those in the USSR. Given these general conclusions, further consideration of certain specific areas is recommended by the report. These include: administrative controls over reactor regulation, reactivity accidents, accidents at low or zero power, multi-unit protection, fires, containment, emergency planning, severe accident phenomena, and graphite-moderated reactors

  3. Maine coast winds

    Energy Technology Data Exchange (ETDEWEB)

    Avery, Richard

    2000-01-28

    The Maine Coast Winds Project was proposed for four possible turbine locations. Significant progress has been made at the prime location, with a lease-power purchase contract for ten years for the installation of turbine equipment having been obtained. Most of the site planning and permitting have been completed. It is expect that the turbine will be installed in early May. The other three locations are less suitable for the project, and new locations are being considered.

  4. Controlled storage for distributed power generation and optimised energy flow in low-voltage mains; Steuerbare Speicher zur Optimierung des Energieflusses in Niederspannungsnetzen mit DEA

    Energy Technology Data Exchange (ETDEWEB)

    Hoeckel, M.; Vollenwyder, R. [Berner Fachhochschule, Hochschule fuer Technik und Informatik (BFH-HTI), Biel (Switzerland); Buholzer, M.; Kreyenbuehl, U. [RIPEnergy AG, Zollikon (Switzerland); Schnyder, G.; Mauchle, P. [Schnyder Ingenieure AG, Huenenberg (Switzerland)

    2005-07-01

    This comprehensive final report for the Swiss Federal Office of Energy (SFOE) examines ways to optimise energy flows in mains networks that include distributed generation facilities. Increasing use of decentralised generation, its effects on the operation of low-voltage mains and the efficient use of the 400 V mains is discussed. The principles of operation and construction of controlled storage installations are discussed and concrete examples of their use in both grid-connected and island operation are quoted. Alternatives to storage are looked at from both the technical and economic points of view. The storage technologies used such as flywheels, supercaps, redox-flow batteries and lead-acid accumulators are briefly assessed and the results of simulations are discussed.

  5. Manpower development for safe operation of nuclear power plant. China. Main steam bypass system operation and maintenance. Task: 6.1.6. Technical report

    International Nuclear Information System (INIS)

    Stubley, P.H.

    1994-01-01

    This mission concentrated on the Steam Bypass system of Qinshan Nuclear Power Plant. The system had experienced spurious opening of the bypass valves, disrupting the steam pressure control and the steam generator level control system. A series of commissioning type tests were defined which should allow the operators to revise the setpoints used in the control of the bypass system, and thus prevent spurious opening while maintaining the desired steam pressure control during power maneuvering. Training also included giving experience from other operating plants on aspects of steam and feedwater systems and components, especially as this experience affected maintenance or gave rise to problems. Steam generated maintenance experience is especially applicable, and a future mission is planned for an expert in this field. In addition other aspects of the Chinese nuclear program was assessed to guide future missions. This included assessment of operating procedures from an availability point of view

  6. Night Wind - Deliverable D.3.2 main simulation report; Grid architecture for wind power production with energy storage through load shifting in refrigerated warehouses

    Energy Technology Data Exchange (ETDEWEB)

    Cronin, Tom; Bindner, Henrik; Zong, Yi

    2008-11-15

    This report represents Deliverable D.3.2 of Work Package 3 in the Night Wind project. The aim of this Work Package was to simulate a cold store (or number of cold stores) within a power system where there is a high degree of wind power penetration. The Night Wind Control System, developed as part of Work Package 5, was to be integrated into the simulations so that the wind power could be 'stored' in the cold store with maximum benefit to the electrical network, utility or cold store owner. To this end, the following have been accomplished: 1) The Night Wind concept has been described in terms of demand side management. 2) Input requirements and data have been specified and collected. Measured data from the existing cold store facility of Partner Logistics has been analysed. 3) Component models for the simulations (including the cold store model itself) have been developed for the simulation platform, IPSYS. 4) The Night Wind Control System (NWCS) from Work Package 5 has been developed so that it finishes computations within two minutes. 5) Controllers including the NWCS) have been operated with the cold store model within IPSYS. 6) Simulations have been performed with the cold store model and an increasing penetration of wind power. This report presents the results of the work undertaken in Work Package 3 which would have benefited from the additional time requested at the project meeting in March 2008, however, this extension of time was not granted. Nevertheless, the work that was possible is considered significantly complete, although it is acknowledged that there has been a delay in the presentation of this report. It should be noted that it was not possible to address the new aspects of Task 3.7 'Verification of simulation results' as there was no implementation of the night wind concept at the demonstration site (Task 7). Verification of the simulation of the present system has, naturally, been carried out and described in this report. (ln)

  7. Analysis of core damage frequency: Nuclear power plant Dukovany, VVER/440 V-213 Unit 1, internal events. Volume 1: Main report

    International Nuclear Information System (INIS)

    Pugila, W.J.

    1994-01-01

    This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for the Dukovany VVER/440 V-213 nuclear power plant, Unit 1. Section 1.1 describes the objectives of this study. Section 1.2 discusses the approach that was used for completing the Dukovany PSA. Section 1.3 summarizes the results of the PSA. Section 1.4 provides a comparison of the results of the Dukovany PSA with the results of other PSAs for different types of reactors worldwide. Section 1.5 summarizes the conclusions of the Dukovany PSA

  8. Electric drive for portable power tools with maximum power supply form the 230 Volt mains; Antriebskonzept fuer Elektrowerkzeuge und den Bezug maximaler Leistung aus dem einphasigen 230-Volt-Netz

    Energy Technology Data Exchange (ETDEWEB)

    Wolff, J. [Karlsruhe Univ. (Germany). Elektrotechnisches Inst.

    2007-07-01

    A new electric drive for hand-held tools and other portable power tools is described in this article. The novel drive concept is designed for the advantageous connection to common 230 V sockets. Based on its special power supply unit and a high drive efficiency a maximum power output about 2700 W can be achieved in continuous operation. Motor speed and gear ratio are adjustable. The drive concept is already used successfully in serial production of core drill machines. (orig.)

  9. Conceptual Design of Main Cooling System for a Fusion Power Reactor with Water Cooled Lithium-Lead Blanket. TW1-TRP-PPCS1, Deliverable 8

    International Nuclear Information System (INIS)

    Natalizio, Antonio; Collen, Jan

    2002-06-01

    The HTS (Heat Transfer System) conceptual design developed for the PPCS (Power-Plant Conceptual Study) plant model is compliant with the single failure criterion - i.e., the failure of a single active component (e.g., pump) will not cause the reactor to shutdown. The system effective availability (capacity factor), however, is only marginally better than that of the SEAFP design, as the number of loops could not be decreased further, due to coolant inventory limitations. The PPCS Plant Model A has about 70 % more fusion power than the SEAFP model. Therefore, keeping the same number of loops as in the SEAFP model would have implied a 70 % larger inventory. To improve plant availability and safety, however, the number of blanket and first wall loops have been reduced from eight to six, implying a further increase in loop inventory of about 25 %. For these and other reasons, the coolant inventory, at risk from a loss-of-coolant accident, has increased significantly, relative to the SEAFP design (∼130 vs. 50 m 3 ). The proposed heat transport system conceptual design meets, or exceeds, all project specifications

  10. The main directions in technology investigation of soid oxide fuel cell in Russian Federal Research Center Institute of Physics & Power Engineering (IPPE)

    Energy Technology Data Exchange (ETDEWEB)

    Ievleva, J.I.; Kolesnikov, V.P.; Mezhertisky, G.S. [and others

    1996-04-01

    The main direction of science investigations for creation of efficient solid oxide fuel cells (SOFC) in IPPE are considered in this work. The development program of planar SOFC with thin-film electrolyte is shown. General design schemes of experimental SOFC units are presented. The flow design schemes of processes for initial materials and electrodes fabrication are shown. The results of investigations for creation thin-film solid oxide electrolyte at porous cathode by magnetron sputtering from complex metal target in oxidative environment are presented.

  11. Carbon as Investment Risk—The Influence of Fossil Fuel Divestment on Decision Making at Germany’s Main Power Providers

    Directory of Open Access Journals (Sweden)

    Dagmar Kiyar

    2015-09-01

    Full Text Available German electricity giants have recently taken high-level decisions to remove selected fossil fuel operations from their company portfolio. This new corporate strategy could be seen as a direct response to the growing global influence of the fossil fuel divestment campaign. In this paper we ask whether the divestment movement currently exerts significant influence on decision-making at the top four German energy giants—E.On, RWE, Vattenfall and EnBW. We find that this is not yet the case. After describing the trajectory of the global fossil fuel divestment campaign, we outline four alternative influences on corporate strategy that, currently, are having a greater impact than the divestment movement on Germany’s power sector. In time, however, clear political decisions and strong civil support may increase the significance of climate change concerns in the strategic management of the German electricity giants.

  12. Device for achieving pressure balance in the steam generator of a power plant in case of a main-steam pipe or a feedwater pipe break

    International Nuclear Information System (INIS)

    Wietelmann, F.

    1978-01-01

    In order to increase the safety in the steam generator of a power plant in case of a pipe break, the possibility of a pressure balance between the feedwater inlet and the initial steam outlet chambers is allowed for. According to the invention, the partition wall separating these two chambers will exhibit several overflow openings, each of which will be provided with a closure and half of which may be opened to one side only, care having been taken that in case of an accident on occurrence of a certain differential pressure they will always be opened to the low-pressure side. As closures caps, which may be swing out of the way, or rupture diaphragms are mentioned. (UWI) 891 HP [de

  13. New multi-microprocessor control system of the main ring magnet power supply for the KEK 12 GeV PS

    International Nuclear Information System (INIS)

    Matsumoto, S.; Sueno, T.; Mikawa, K.; Toda, M.; Baba, H.

    1987-01-01

    The new control computer system has been installed at the last June. The main cpu supervised by the Unix covers man-machine interfacing and correction of current deviation in periodic control algorithm. The two sub-cpu are linked by a LAN and supported by a real time multi-task monitor. The one as the output process controller distributes 15 control patterns to 16-bit D/A converters at every 1.67 ms synchronized 6 phase ac line. The other as the input logs B Qf and Qd magnet current and voltage by 7 sets of 16-bit ADC at the same clock. Resulting precision of the currents from beam injection to flat top would be estimated at about a resolution limit of ADC except for current ripple. Ripple currents estimated at several times of an intrinsic ripple in the DCCT

  14. Main internal dose-forming factors for inhabitants of contaminated regions at current phase of the Chernobyl nuclear power plant accident (Kyiv region as an example)

    International Nuclear Information System (INIS)

    Vasilenko, V.V.; Nechajev, S.Yu.; Tsigankov, M.Ya.; And others

    2015-01-01

    Objective of this work is revealing of main dose"forming factors of internal doses for inhabitants of contaminated regions of Kyiv region relying on the results of integral dosimetric monitoring. Three villages have been chosen for the investigation. They are: Raghivka, Zelena Poliana (Poliske district), Karpylivka (Ivankiv district). Twice a year, in May and in October those villages' residents were inspected for content of incorporated "1"3"7Cs. They were measured by direct method at the place of residence with the help of whole body counters (WBC). The principal food samples were collected for detection of "9"0Sr and "1"3"7Cs content. Those villages' inhabitants were interviewed about food consumption levels. Mathematical, dosimetric and radio-chemical methods were used in this work. The estimation of internal doses due to intake of "1"3"7Cs by ingestion of milk and potatoes are in the range 0.3-34% of doses estimated on the base of WBC data. The contribution to the dose of internal exposure from intake of "1"3"7Cs with the milk consumption is no more than two times higher than the contribution of potatoes consumption in the case of equal consumption levels of these products. Contributions to the dose of internal exposure from intake of "9"0Sr with milk and potatoes consumptions are approximately similar. Consumption of mushrooms and other wild nature products by inhabitants from the inspected settlements is the main forming factor of internal dose due to "1"3"7Cs intake

  15. A Study of the Link between Cosmic Rays and Clouds with a Cloud Chamber at the CERN PS

    CERN Multimedia

    Laakso, L K; Lehtipalo, K; Miettinen, P K; Duarte branco da silva santos, F; Stojkov, Y; Jud, W; Wurm, F; Pinterich, T; Dommen, J; Curtius, J; Kreissl, F C; Minginette, P; Azeredo lima, J M; Kulmala, M T; Petaja, T T; Volkamer, R M; Schafer, M; Rodrigues tome, A; Viisanen, Y A; Onnela, A T O; Kristic, R; Ehrhart, S K; Amorim, A J; Maksumov, O; Kupc, A; Sitals, R P; Dunne, E M; Riipinen, I A; Downard, A J; Virtanen, A; Tsagkogeorgas, G; Schuchmann, S; Kvashnin, A; Hansel, A; Gonzalez carracedo, L R; Vrtala, A; Schallhart, S; Yan, C; Stratmann, F; Pinto mogo, S I; Makhmutov, V; Riccobono, F; Weingartner, E P; Kurten, C A; Rondo, L; Ruuskanen, T M; Finkenzeller, H F; Laaksonen, A J; De menezes, L; Hauser, D; Kajos, M K; Schmitt, T M; Mathot, S; Wasem, A; Guida, R; Metzger, A E; Baltensperger, U; Kirkby, J; Duplissy, J; Franchin, A; Rorup, B; Flagan, R C; Wex, H D

    2002-01-01

    Three recent independent observations suggest that galactic cosmic rays may exert a significant influence on the climate. Firstly, satellite data suggest a positive correlation between variations of cosmic ray intensity and the fraction of Earth covered by low clouds. Secondly, palaeoclimatic data provide extensive evidence for an association between cosmic ray intensity and climate over the last 10 kyr and at earlier times. Finally, the presence of ion-induced nucleation of new aerosol in the atmosphere is supported by recent observations. If cosmic rays do indeed enhance aerosol production and low cloud formation, this could exert a strong cooling influence on the radiative energy balance of Earth. Physical mechanisms by which cosmic rays may affect aerosol and clouds have been proposed and modelled, but definitive experiments are lacking. The aim of CLOUD is to investigate the nature and significance of cosmic ray-aerosol-cloud mechanisms under controlled laboratory conditions using the T11 beam at the CER...

  16. Determination of the Neutron Fluence, the Beam Characteristics and the Backgrounds at the CERN-PS TOF Facility

    CERN Multimedia

    Leal, L C; Kitis, G; Guber, K H; Quaranta, A; Koehler, P E

    2002-01-01

    In the scope of our programme we propose to start in July 2000 with measurements on elements of well known cross sections, in order to check the reliability of the whole experimental installation at the CERN-TOF facility. These initial exploratory measurements will provide the key-parameters required for the further experimentation at the CERN-TOF neutron beam. The neutron fluence and energy resolution will be determined as a function of the neutron kinetic energy by reproducing standard capture and fission cross sections. The measurements of capture cross sections on elements with specific cross section features will allow to us to disentangle the different components of backgrounds and estimate their level in the experimental area. The time-energy calibration will be determined and monitored with a set of monoenergetic filters as well as by the measurements of elements with resonance-dominated cross sections. Finally, in this initial phase the behaviour of several detectors scheduled in successive measureme...

  17. Electron-cloud simulation studies for the CERN-PS in the framework of the LHC Injectors Upgrade project

    CERN Document Server

    Rioja Fuentelsaz, Sergio

    The present study aims to provide a consistent picture of the electron cloud effect in the CERN Proton Synchrotron (PS) and to investigate possible future limitations due to the requirements foreseen by the LHC Injectors Upgrade (LIU) project. It consists of a complete simulation survey of the electron cloud build-up in the different beam pipe sections of the ring depending on several controllable beam parameters and vacuum chamber surface properties, covering present and future operation parameters. As the combined function magnets of the accelerator constitute almost the $80\\%$ in length of the ring, the implementation of a new feature for the simulation of any external magnetic field on the PyECLOUD code, made it possible to perform this study. All the results of the simulations are given as a function of the vacuum chamber surface properties in order to deduce them, both locally and globally, when compared with experimental data. In a first step, we characterize locally the maximum possible number of ...

  18. A study of the link between cosmic rays and clouds with a cloud chamber at the CERN PS

    CERN Document Server

    Fastrup, B; Lillestøl, Egil; Thorn, E; Bosteels, Michel; Gonidec, A; Harigel, G G; Kirkby, Jasper; Mele, S; Minginette, P; Nicquevert, Bertrand; Schinzel, D; Seidl, W; Grundsøe, P; Marsh, N D; Polny, J; Svensmark, H; Viisanen, Y; Kurvinen, K L; Orava, Risto; Hämeri, K; Kulmala, M; Laakso, I; Mäkelä, J M; O'Dowd, C D; Afrosimov, V; Basalaev, A; Panov, M; Laaksonen, B D; Joutsensaari, J; Ermakov, V; Makhmutov, V S; Maksumov, O; Pokrevsky, P; Stozhkov, Yu I; Svirzhevsky, N S; Carslaw, K; Yin, Y; Trautmann, T; Arnold, F; Wohlfrom, K H; Hagen, D; Schmitt, J; Whitefield, P; Aplin, K; Harrison, R G; Bingham, R; Close, Francis Edwin; Gibbins, C; Irving, A; Kellett, B; Lockwood, M; Petersen, D; Szymanski, W W; Wagner, P E; Vrtala, A; CERN. Geneva. SPS-PS Experiments Committee

    2000-01-01

    Recent satellite data have revealed a surprising correlation between galactic cosmic ray (GCR) intensity and the fraction of the Earth covered by clouds. If this correlation were to be established by a causal mechanism, it could provide a crucial step in understanding the long-sought mechanism connecting solar and climate variability. The Earth's climate seems to be remarkably sensitive to solar activity, but variations of the Sun's electromagnetic radiation appear to be too small to account for the observed climate variability. However, since the GCR intensity is strongly modulated by the solar wind, a GCR-cloud link may provide a sufficient amplifying mechanism. Moreover if this connection were to be confirmed, it could have profound consequences for our understanding of the solar contributions to the current global warming. The CLOUD (Cosmics Leaving OUtdoor Droplets) project proposes to test experimentally the existence a link between cosmic rays and cloud formation, and to understand the microphysical me...

  19. Evolution of High Intensity Beams in the CERN PS Booster after H⁻ Injection and Phase Space Painting

    CERN Document Server

    Cieslak-Kowalska, Magdalena; Benedetto, Elena; Bracco, Chiara

    2016-01-01

    With the LHC Injector Upgrade (LIU) project, the injection energy of PS Booster (PSB) ' first circular accelerator in the LHC injector chain ' will be raised from 50 MeV to 160 MeV and the present multiturn injection will be upgraded to H⁻ injection with transverse and longitudinal painting. In the scope of this project, it is planned to double the beam intensities, profiting from the fact that the βγ2 factor will be two times larger (0.35 at 50 MeV and 0.71 at 160 MeV), so the resulting tune spread driven by a direct space charge should remain similar. This paper describes the feasibility to double the intensity of high intensity and large emittance beams, looking into the evolution under space charge and taking into account losses constrains in the ring and in the extraction lines.

  20. Experimental results on one-pion neutral current reaction in all channels induced by antineutrinos at CERN PS

    CERN Document Server

    Erriquez, O; Bullock, F W; Cavalli, D; Engel, J P; Fogli-Muciaccia, M T; Gamba, D; Guyonnet, J L; Halsteinslid, A; Henderson, R C W; Huss, D; Jones, T W; Marzari-Chiesa, A; Myklebost, K; Natali, S; Nuzzo, S; Paty, M; Pullia, A; Riccati, L; Riester, J L; Rognebakke, A; Rollier, M; Romero, A

    1980-01-01

    Single pion production, in antineutrino-nucleon interactions via the neutral current, has been studied in the bubble chamber Gargamelle, filled with propane. Complete analysis of the secondaries, including pi /sup 0/'s, has allowed a detailed study of all channels. After background and nuclear corrections, results are obtained which can be interpreted in terms of isospin structure of the neutral weak current and of the Salam-Weinberg angle. Agreement is found with the currently accepted value of sin/sup 2/ theta /sub w/ and the data suggest an important contribution of I=/sup 3///sub 2/ final states. (11 refs).

  1. Wall-Current-Monitor based Ghost and Satellite Bunch Detection in the CERN PS and the LHC Accelerators

    CERN Document Server

    Steinhagen, R J; Belleman, J; Bohl, T; Damerau, H

    2012-01-01

    While most LHC detectors and instrumentation systems are optimised for a nominal bunch spacing of 25 ns, the LHC RF cavities themselves operate at the 10th harmonic of the maximum bunch frequency. Due to the beam production scheme and transfers in the injector chain, part of the nominally ‘empty’ RF buckets may contain particles, referred to as ghost or satellite bunches. These populations must be accurately quantified for high-precision experiments, luminosity calibration and control of parasitic particle encounters at the four LHC interaction points. This contribution summarises the wall-current-monitor based ghost and satellite bunch measurements in CERN’s PS and LHC accelerators. Instrumentation set-up, post-processing and achieved performance are discussed.

  2. A microprocessor-based system for continuous monitoring of radiation levels around the CERN PS and PSB accelerators

    Science.gov (United States)

    Agoritsas, V.; Beck, F.; Benincasa, G. P.; Bovigny, J. P.

    1986-06-01

    This paper describes a new beam loss monitor system which has been installed in the PS and PSB machines, replacing an earlier system. The new system is controlled by a microprocessor which can operate independently of the accelerator control system, though setting up and central display are usually done remotely, using the standard control system facilities.

  3. Microprocessor-based system for continuous monitoring of radiation levels around the CERN PS and PSB accelerators

    Energy Technology Data Exchange (ETDEWEB)

    Agoritsas, V.; Beck, F.; Benincasa, G.P.; Bovigny, J.P.

    1986-06-01

    This paper describes a new beam loss monitor system which has been installed in the PS and PSB machines, replacing an earlier system. The new system is controlled by a microprocessor which can operate independently of the accelerator control system, though setting up and central display are usually done remotely, using the standard control system facilities.

  4. Influence of Laser Radiation Power Density on the Intensity of Spectral Lines for Main Components in a Clay Laser-Induced Plasma

    Science.gov (United States)

    Anufrik, S. S.; Kurian, N. N.; Znosko, K. F.; Belkov, M. V.

    2018-05-01

    We have studied the intensity of the spectral lines for the main components in clay: Al I 309.4 nm, Al II 358.7 nm, Mg II 279.6 nm, Ti II 323.6 nm vs. the position of the object relative to the focus of the optical system when the samples are exposed to single laser pulses from a YAG:Nd3+ laser. We have determined the permissible ranges for positioning the object relative to the focus of the optical system (positive and negative defocusing) for which there is practically no change in the reproducibility of the intensity for the spectral lines for red and white clay samples. We show that the position of the object relative to the focus of the optical system should be within the range ΔZ ±1.5 mm for optimal laser pulse energies for the analyte spectral lines. We have calculated the radiation flux density for different laser pulse energies and different distances from the focus to the object. We have shown experimentally that reducing the radiation flux density leads to a decrease in the intensity of the analyte spectral lines.

  5. ANALYSIS AND PARAMETRIC OPTIMIZATION OF ENERGY-AND-TECHNOLOGY UNITS ON THE BASIS OF THE POWER EQUIPMENT OF COMPRESSOR PLANTS OF MAIN GAS PIPELINES

    Directory of Open Access Journals (Sweden)

    V. A. Sednin

    2017-01-01

    Full Text Available On the basis of the gas compressor units of compressor plants of a main gas pipeline mathematical models of the macro-level were generated for analysis and parametric optimization of combined energy-and-technology units. In continuation of the study these models was applied to obtain the regression dependencies. For this purpose, a numerical experiment was used which had been designed with the use of regression analysis mathematical tool, which assumes that the test results should represent independent, normally distributed, random variables with approximately equal variance. Herewith we study the dependence of the optimization criterion on the value of control parameters (factors. Planning, conducting and processing of results of the experiment was conducted in the following sequence: choice of the optimization criteria, selection of control parameters (factors, encoding factors, the matrix of experiment compiling, assessing significance of regression coefficients, testing the adequacy of the model and reproducibility of the experiments. As the optimization criteria the electricity capacity and efficiency of combined energy-technology units were adopted. As control parameters for the installation with a gas-expansion-and-generator machine the temperature of the fuel gas before the expander, the pressure of the fuel gas after the expander and the temperature of the air supplied to the compressor of the engine were adopted, while for the steam turbine the adopted optimization criteria were compression in the compressor of the engine, the steam consumption for the technology and the temperature of the air supplied to the compressor of the engine. The application of the outlined methodological approach makes it possible to obtain a simple polynomial dependence, which significantly simplify the procedures of analysis, parametric optimization and evaluation of efficiency in the feasibility studies of the options of construction of the energy

  6. Visualizing the characteristics of a work process being observed from the main control room of nuclear power plants - identifying underlying requirements

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jinkyun; Jung, Wondea [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    One of the disseminated approaches is to identify and manage vulnerable tasks (i.e., error-prone tasks) by applying many kinds of human reliability assessment (HRA) techniques. That is, if HRA practitioners are able to identify plausible error forcing factors (e.g., performance shaping factors; PSFs) under a given task context, effective countermeasures that are helpful for reducing the possibility of human error can be drawn by deducing how to eliminate the associated PSFs. In order to reduce the variability of HRA results, the development of an objective criterion for determining the level of each PSF could be the most plausible countermeasure. In order to address this issue, this paper applied a process mining technique to the analysis of communication logs gathered from main control room (MCR) crews in NPPs, which could be useful for visualizing their characteristics in terms of the Work process. In this study, before providing additional information that is helpful for HRA practitioners in determining the quality of the Work process, three kinds of underlying requirements are identified. They are: (1) an ability to describe the flow of a work, (2) an ability to incorporate time and spatial information into the flow of a work, and (3) an ability to identify the flow of symptoms and/or knowledge being employed by an MCR crew. In order to satisfy these requirements, a couple of techniques can be used. This might allow partial pooling of log information according to how the information can be clustered.' In other words, the process mining technique is very useful for discovering the flow of a work being involved in a given situation, it is strongly expected that the analysis of communication logs that allow us to understand what and how they did in order to cope with a situation at hand. If so, it is possible to visualize necessary information that is essential for minimizing the variability of HRA practitioners who have to determine the quality of the Work

  7. Visualizing the characteristics of a work process being observed from the main control room of nuclear power plants - identifying underlying requirements

    International Nuclear Information System (INIS)

    Park, Jinkyun; Jung, Wondea

    2015-01-01

    One of the disseminated approaches is to identify and manage vulnerable tasks (i.e., error-prone tasks) by applying many kinds of human reliability assessment (HRA) techniques. That is, if HRA practitioners are able to identify plausible error forcing factors (e.g., performance shaping factors; PSFs) under a given task context, effective countermeasures that are helpful for reducing the possibility of human error can be drawn by deducing how to eliminate the associated PSFs. In order to reduce the variability of HRA results, the development of an objective criterion for determining the level of each PSF could be the most plausible countermeasure. In order to address this issue, this paper applied a process mining technique to the analysis of communication logs gathered from main control room (MCR) crews in NPPs, which could be useful for visualizing their characteristics in terms of the Work process. In this study, before providing additional information that is helpful for HRA practitioners in determining the quality of the Work process, three kinds of underlying requirements are identified. They are: (1) an ability to describe the flow of a work, (2) an ability to incorporate time and spatial information into the flow of a work, and (3) an ability to identify the flow of symptoms and/or knowledge being employed by an MCR crew. In order to satisfy these requirements, a couple of techniques can be used. This might allow partial pooling of log information according to how the information can be clustered.' In other words, the process mining technique is very useful for discovering the flow of a work being involved in a given situation, it is strongly expected that the analysis of communication logs that allow us to understand what and how they did in order to cope with a situation at hand. If so, it is possible to visualize necessary information that is essential for minimizing the variability of HRA practitioners who have to determine the quality of the Work

  8. Decontamination of main coolant pumps

    International Nuclear Information System (INIS)

    Roofthooft, R.

    1988-01-01

    Last year a number of main coolant pumps in Belgian nuclear power plants were decontaminated. A new method has been developed to reduce the time taken for decontamination and the volume of waste to be treated. The method comprises two phases: Oxidation with permanganate in nitric acid and dissolution in oxalic acid. The decontamination of main coolant pumps can now be achieved in less than one day. The decontamination factors attained range between 15 and 150. (orig.) [de

  9. Noise annoyances from wind power: Survey of the population living close to a wind power plant. Final report: Part 3 Main study; Stoerningar fraan vindkraft: undersoekning bland maenniskor boende i naerheten av vindkraftverk. Slutrapport: Del 3 Huvudstudie

    Energy Technology Data Exchange (ETDEWEB)

    Pedersen, Eja [Halmstad Univ., Halmstad (Sweden). School of Business and Engineering; Persson-Waye, K. [Goeteborg Univ., Goeteborg (Sweden). Dept. of Environmental Medicine

    2002-02-01

    To evaluate the occurrence of annoyance from wind turbines, a study was performed in Laholm in May 2000. The aim was to obtain dose response relationships between calculated sound levels and noise annoyance and appropriate sound description as well as analysing the influence of other variables on noise annoyance. A questionnaire survey was performed in 6 areas comprising 16 wind turbines, of which 14 had an effect of 600 kW. The purpose of the study was masked. Among questions on living conditions in the countryside, questions directly related to wind turbines were included. The study population (n=518) comprised one randomly selected subject between the ages of 18 to 75 years in each household living within a calculated wind turbine sound level of 25 to 40 dBA. The response rate was 68.7% (n=356). Calculated distributions of A-weighted sound level were performed for each area and plotted on geographical maps in 2.5 dBA steps. Each dwelling could thus be given a sound level within an interval of 2.5 dBA. The most frequently occurring source of noise annoyance was noise from rotor blades. The proportions of respondents annoyed by noise increased with calculated sound level. Among respondents exposed to sound levels of 35.0-37.5 dBA, 43% responded themselves to be rather or much annoyed. A-weighted sound level was only one variable explaining annoyance. Annoyance was correlated to a larger extent by the intrusiveness of the sound character swishing. Noise annoyance was interrelated to the respondents' opinion of the visual impact of wind turbines, while attitude towards wind power in general had no greater influence. Disturbance of spoilt view was reported to a similar degree as noise disturbance. Further investigations are needed to clarify factors of importance for the disturbance of view. All the wind turbines in the study had constant rotation speed. The greater wind turbines that are now erected often have variable speed, which may lead to a sound

  10. Noise annoyances from wind power: Survey of the population living close to a wind power plant. Final report: Part 3 Main study; Stoerningar fraan vindkraft: undersoekning bland maenniskor boende i naerheten av vindkraftverk. Slutrapport: Del 3 Huvudstudie

    Energy Technology Data Exchange (ETDEWEB)

    Pedersen, Eja [Halmstad Univ., Halmstad (Sweden). School of Business and Engineering; Persson-Waye, K [Goeteborg Univ., Goeteborg (Sweden). Dept. of Environmental Medicine

    2002-02-01

    To evaluate the occurrence of annoyance from wind turbines, a study was performed in Laholm in May 2000. The aim was to obtain dose response relationships between calculated sound levels and noise annoyance and appropriate sound description as well as analysing the influence of other variables on noise annoyance. A questionnaire survey was performed in 6 areas comprising 16 wind turbines, of which 14 had an effect of 600 kW. The purpose of the study was masked. Among questions on living conditions in the countryside, questions directly related to wind turbines were included. The study population (n=518) comprised one randomly selected subject between the ages of 18 to 75 years in each household living within a calculated wind turbine sound level of 25 to 40 dBA. The response rate was 68.7% (n=356). Calculated distributions of A-weighted sound level were performed for each area and plotted on geographical maps in 2.5 dBA steps. Each dwelling could thus be given a sound level within an interval of 2.5 dBA. The most frequently occurring source of noise annoyance was noise from rotor blades. The proportions of respondents annoyed by noise increased with calculated sound level. Among respondents exposed to sound levels of 35.0-37.5 dBA, 43% responded themselves to be rather or much annoyed. A-weighted sound level was only one variable explaining annoyance. Annoyance was correlated to a larger extent by the intrusiveness of the sound character swishing. Noise annoyance was interrelated to the respondents' opinion of the visual impact of wind turbines, while attitude towards wind power in general had no greater influence. Disturbance of spoilt view was reported to a similar degree as noise disturbance. Further investigations are needed to clarify factors of importance for the disturbance of view. All the wind turbines in the study had constant rotation speed. The greater wind turbines that are now erected often have variable speed, which may lead to a sound comprising

  11. DER 86: main facts

    International Nuclear Information System (INIS)

    1987-01-01

    This report presents the important facts among the studies carried out by the Direction des Etudes et Recherches (E.D.F.): new applications of electric power for customers, protection of environment, classical equipments for power plants and nuclear equipments, monitoring and control of power plants, electrical equipments, development and operation of electrical networks, informatics and office automation [fr

  12. International benchmark for coupled codes and uncertainty analysis in modelling: switching-Off of one of the four operating main circulation pumps at nominal reactor power at NPP Kalinin unit 3

    International Nuclear Information System (INIS)

    Tereshonok, V. A.; Nikonov, S. P.; Lizorkin, M. P.; Velkov, K; Pautz, A.; Ivanov, V.

    2008-01-01

    The paper briefly describes the Specification of an international NEA/OECD benchmark based on measured plant data. During the commissioning tests for nominal power at NPP Kalinin Unit 3 a lot of measurements of neutron and thermo-hydraulic parameters have been carried out in the reactor pressure vessel, primary and the secondary circuits. One of the measured data sets for the transient 'Switching-off of one Main Circulation Pump (MCP) at nominal power' has been chosen to be applied for validation of coupled thermal-hydraulic and neutron-kinetic system codes and additionally for performing of uncertainty analyses as a part of the NEA/OECD Uncertainty Analysis in Modeling Benchmark. The benchmark is opened for all countries and institutions. The experimental data and the final specification with the cross section libraries will be provided to the participants from NEA/OECD only after official declaration of real participation in the benchmark and delivery of the simulated results of the transient for comparison. (Author)

  13. Main Memory DBMS

    NARCIS (Netherlands)

    P.A. Boncz (Peter); L. Liu (Lei); M. Tamer Özsu

    2008-01-01

    htmlabstractA main memory database system is a DBMS that primarily relies on main memory for computer data storage. In contrast, normal database management systems employ hard disk based persisntent storage.

  14. Estimating the response times of human operators working in the main control room of nuclear power plants based on the context of a seismic event – A case study

    International Nuclear Information System (INIS)

    Park, Jinkyun; Kim, Yochan; Kim, Jung Han; Jung, Wondea; Jang, Seung Cheol

    2015-01-01

    Highlights: • Response times under seismic events are necessary for human reliability analysis. • Conceptual framework to estimate response times under a seismic event is suggested. • Four kinds of representative contexts in seismic events are considered. • Rules for estimating response times on the representative contexts are extracted. - Abstract: After the Fukushima accident, a couple of novel issues have raised in terms of the safety assessment of nuclear power plants (NPPs). This means that the performance of human operators should be properly evaluated under an extreme event. However, it is unrealistic to collect a sufficient amount of human performance data from a real event, such as a great earthquake. As one of the promising solutions, a conceptual framework is suggested in this paper, which is helpful for estimating the response time data of human operators working in the main control room of NPPs under a seismic event. To this end, the four kinds of representative contexts that could be anticipated from seismic events are identified. Then the response times of human operators who are faced with similar contexts are reviewed from existing literatures and databases. As a result, a couple of rules that allow us to extrapolate the response times of human operators under seismic events are extracted. Although underlying rationales being used for determining these rules are still arguable, it is expected that response times under seismic events could be properly understood along with accumulating those of human operators against non-seismic conditions

  15. Maine's Employability Skills Program

    Science.gov (United States)

    McMahon, John M.; Wolffe, Karen E.; Wolfe, Judy; Brooker, Carrie

    2013-01-01

    This Practice Report describes the development and implementation of the "Maine Employability Skills Program," a model employment program developed by the Maine Division for the Blind and Visually Impaired (DBVI). The program was designed to support the efforts of the chronically unemployed or underemployed. These consumers were either…

  16. Turbine main engines

    CERN Document Server

    Main, John B; Herbert, C W; Bennett, A J S

    1965-01-01

    Turbine Main Engines deals with the principle of operation of turbine main engines. Topics covered include practical considerations that affect turbine design and efficiency; steam turbine rotors, blades, nozzles, and diaphragms; lubricating oil systems; and gas turbines for use with nuclear reactors. Gas turbines for naval boost propulsion, merchant ship propulsion, and naval main propulsion are also considered. This book is divided into three parts and begins with an overview of the basic mode of operation of the steam turbine engine and how it converts the pressure energy of the ingoing ste

  17. Maine highway safety plan

    Science.gov (United States)

    2010-01-01

    Each September 1, the MeBHS must provide NHTSA a comprehensive plan to reduce : traffic crashes and resulting deaths, injuries and property damage. The Highway Safety : Plan (HSP) serves as Maines application for available federal funds for these ...

  18. Maine Field Station

    Data.gov (United States)

    Federal Laboratory Consortium — In 2000 NOAA's National Marine Fisheries Service established the Maine Field Station in Orono, ME to have more direct involvement in the conservation of the living...

  19. Maine's forests 2008

    Science.gov (United States)

    George L. McCaskill; William H. McWilliams; Charles J. Barnett; Brett J. Butler; Mark A. Hatfield; Cassandra M. Kurtz; Randall S. Morin; W. Keith Moser; Charles H. Perry; Christopher W. Woodall

    2011-01-01

    The second annual inventory of Maine's forests was completed in 2008 after more than 3,160 forested plots were measured. Forest land occupies almost 17.7 million acres, which represents 82 percent of the total land area of Maine. The dominant forest-type groups are maple/beech/yellow birch, spruce/fir, white/red/jack pine, and aspen/white birch. Statewide volume...

  20. Maine Forests 2013

    Science.gov (United States)

    George L. McCaskill; Thomas Albright; Charles J. Barnett; Brett J. Butler; Susan J. Crocker; Cassandra M. Kurtz; William H. McWilliams; Patrick D. Miles; Randall S. Morin; Mark D. Nelson; Richard H. Widmann; Christopher W. Woodall

    2016-01-01

    The third 5-year annualized inventory of Maine's forests was completed in 2013 after more than 3170 forested plots were measured. Maine contains more than 17.6 million acres of forest land, an area that has been quite stable since 1960, covering more than 82 percent of the total land area. The number of live trees greater than 1 inch in diameter are approaching 24...

  1. Main sequence mass loss

    International Nuclear Information System (INIS)

    Brunish, W.M.; Guzik, J.A.; Willson, L.A.; Bowen, G.

    1987-01-01

    It has been hypothesized that variable stars may experience mass loss, driven, at least in part, by oscillations. The class of stars we are discussing here are the δ Scuti variables. These are variable stars with masses between about 1.2 and 2.25 M/sub θ/, lying on or very near the main sequence. According to this theory, high rotation rates enhance the rate of mass loss, so main sequence stars born in this mass range would have a range of mass loss rates, depending on their initial rotation velocity and the amplitude of the oscillations. The stars would evolve rapidly down the main sequence until (at about 1.25 M/sub θ/) a surface convection zone began to form. The presence of this convective region would slow the rotation, perhaps allowing magnetic braking to occur, and thus sharply reduce the mass loss rate. 7 refs

  2. Safety-engineering concepts for process control in the chemical industry and in power plants. VDE Regional Association of Frankfurt/Main, VDI Regional Association of Frankfurt/Main-Darmstadt, Study Group meeting from March 9-30, 1987. Sicherheitskonzepte der Prozessleittechnik in verfahrenstechnischen Anlagen und in Kraftwerken. VDE-Bezirksverein Frankfurt am Main, VDI-Bezirksverein Frankfurt a. M. -Darmstadt Arbeitsgemeinschaft vom 9. 3. bis 30. 3. 1987

    Energy Technology Data Exchange (ETDEWEB)

    Forst, H J [ed.

    1987-01-01

    Process instrumentation and control is a task relying to a very large extent on on-line process control systems for continuous monitoring and control. Stored-program control systems are one of the smaller systems available for process measuring and control, and are currently used for enhancing the safety of chemical plants and power plants, particularly nuclear power plants. The contributions in this book deal with basic safety engineering concepts and with methods for early detection of faults or critical states of a plant or system. (DG).

  3. FERMILAB: Main Injector

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The Fermilab Main Injector (FMI) project is the centerpiece of the Laboratory's Fermilab III programme for the 1990s. Designed to support a luminosity of at least 5x10 31 cm -2 s -1 in the Tevatron collider, it will also provide new capabilities for rare neutral kaon decay and neutrino oscillation studies. The Fermilab Main Injector 8-150 GeV synchrotron is designed to replace the existing Main Ring which seriously limits beam intensities for the Tevatron and the antiproton production target. The project has passed several significant milestones and is now proceeding rapidly towards construction. The project received a $11.65M appropriation in 1992 and has been given $15M for the current fiscal year. Through the Energy Systems Acquisition Advisory Board (ESAAB) process, the US Department of Energy (DoE) has authorized funds for construction of the underground enclosure and service building where the Main Injector will touch the Tevatron, and to the preparation of bids for remaining project construction

  4. FERMILAB: Main Injector

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1993-06-15

    The Fermilab Main Injector (FMI) project is the centerpiece of the Laboratory's Fermilab III programme for the 1990s. Designed to support a luminosity of at least 5x10{sup 31} cm{sup -2} s{sup -1} in the Tevatron collider, it will also provide new capabilities for rare neutral kaon decay and neutrino oscillation studies. The Fermilab Main Injector 8-150 GeV synchrotron is designed to replace the existing Main Ring which seriously limits beam intensities for the Tevatron and the antiproton production target. The project has passed several significant milestones and is now proceeding rapidly towards construction. The project received a $11.65M appropriation in 1992 and has been given $15M for the current fiscal year. Through the Energy Systems Acquisition Advisory Board (ESAAB) process, the US Department of Energy (DoE) has authorized funds for construction of the underground enclosure and service building where the Main Injector will touch the Tevatron, and to the preparation of bids for remaining project construction.

  5. Main designations and attributions

    International Nuclear Information System (INIS)

    2010-01-01

    The chapter presents the main designations and attributions of the LNMRI - Brazilian National Laboratory of Metrology of Ionizing Radiation, the Cooperative Center in Radiation Protection and Medical Preparations for Accidents with Radiation; the Treaty for fully banning of nuclear tests and the Regional Center for Training of IAEA

  6. Maine Bouguer Gravity Grid

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A 2 kilometer Bouguer anomaly grid for the state of Maine. Number of columns is 197 and number of rows is 292. The order of the data is from the lower left to the...

  7. Renovating the Main Building

    CERN Multimedia

    CERN Bulletin

    2010-01-01

    CERN's "Main Building" is exactly that. The Organization's central hub, with hundreds of staff and visitors passing through its doors every day, will soon be getting a well-earned facelift. Refurbishment work will proceed in phases, starting with the Salle des Pas Perdus, the concourse between the Council Chamber and the Main Auditorium. By the end of August, informal seating areas will be installed, electronic display panels will provide practical information and improved sound insulation will enhance conditions in the auditoria and surrounding meeting rooms.   In light green the area that will undergo the facelift. Work will start in July. The ground floor is home to the entrance to Restaurant No. 1, the bank, the post office, the travel agent, the Users Office, the Staff Association, the notice boards etc. Step up to the first floor to access CERN's largest lecture theatre, the Council Chamber and its "Pas Perdus" lobby. Everyone who works at or visits CERN i...

  8. Fermilab Main Injector plan

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1990-07-15

    The Fermilab Main Injector is the centrepiece of the 'Fermilab III' scheme to significantly upgrade the Laboratory's existing accelerator complex. The new accelerator is designed to provide increased particle beam levels to boost the collision rate in the Tevatron proton-antiproton collider (luminosity in excess of 5 x 10{sup 31} per sq cm per s) and, if approved, would provide increased flexibility in all areas of high energy physics research.

  9. Fermilab Main Injector plan

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The Fermilab Main Injector is the centrepiece of the 'Fermilab III' scheme to significantly upgrade the Laboratory's existing accelerator complex. The new accelerator is designed to provide increased particle beam levels to boost the collision rate in the Tevatron proton-antiproton collider (luminosity in excess of 5 x 10 31 per sq cm per s) and, if approved, would provide increased flexibility in all areas of high energy physics research

  10. Project evaluation: main characteristics

    OpenAIRE

    Moutinho, Nuno

    2010-01-01

    — The evaluation process of real investment projects must consider not only the traditional financial approach, but also non-financial aspects. Non financial analysis can provide additional relevant information about projects. We investigate financial and non-financial areas most relevant in project appraisal. We present main critical success factors and areas of analysis that lead to the perception of project success. Finally, companies are segmented to verify its financial and non-financial...

  11. Marketing Maine Tablestock Potatoes

    OpenAIRE

    Berney, Gerald; Grajewski, Gregory; Hinman, Don; Prater, Marvin E.; Taylor, April

    2010-01-01

    The Marketing Services Division of USDA’s Agricultural Marketing Service (AMS) was asked by USDA’s Agricultural Research Service (ARS) National Program Leader and ARS’s New England Soil and Water Research Laboratory personnel to help with existing efforts to assist Maine fresh potato farmers in their search for alternative marketing strategies, and reverse the recent decline in the profitability of their operations. ARS researchers previously had conducted an exhaustive study defining possibl...

  12. Summary of main points

    International Nuclear Information System (INIS)

    2006-01-01

    In conjunction with its 6. annual meeting, the WPDD in close co-operation with the FSC held a Topical session on 'Stakeholder Involvement in Decommissioning' on November 14, 2005. The session was attended by 36 participants totally representing 14 NEA member countries and 2 international organisations. Two keynote addresses were given at the Topical Session. The first one treated of what is needed for robust decisions and how to bring all stakeholders into the debate. In the second keynote address a summary was made on what have been said on stakeholder involvement in decommissioning during earlier meetings of the WPDD. The main part of the session was then devoted to views from different stakeholders regarding their role and their involvement. This part contained viewpoints from local communities (Kaevlinge in Sweden and Port Hope in Canada), authorities (Scottish Executive and CSNC) and operators (EDF from France and EWN from Germany). Case studies from the decommissioning of Dounrey in the UK and from Trojan and Main Yankee in the USA were presented in the end part of the Topical session followed by a summary and lessons learnt report by the Rapporteur. A detailed programme of the Topical session can be seen in Appendix 1

  13. Impact of Investments in Generating Units and Transmission and Distribution Power Grids by 2025 on Voltage Stability and Branches Load in ENERGA SA Operational Territory – Main Findings of Research Project

    Directory of Open Access Journals (Sweden)

    Dominik Falkowski

    2013-03-01

    Full Text Available The article summarizes a research project which was conducted in order to ensure what will be the influence of future investments and changes in the Polish Power System on the stability and functionality of the ENERGA SA distribution grid system. Development of the ENERGA SA distribution grid system was also included. Only stable states were tested for various cases of system load and generation in power plants (the Nuclear Power Plant in Żarnowiec was taken into account and also in wind farms. The system was also tested in N-1 and N-2 states. The result of this study is an overall evaluation of the ENERGA SA distribution grid condition, as well as the identification of potential weak points inside this structure.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-03-01

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

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

    International Nuclear Information System (INIS)

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

    1995-03-01

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

  16. Improvement of main control room

    International Nuclear Information System (INIS)

    Chae, Sung Ki; Ham, Chang Sik; Kwon, Ki Chun

    1991-07-01

    Information display system, advanced alarm system and fiber optical communication system were developed to improve the main control room in nuclear power plant. Establishing the new hierachical information structure of plant operation data, plant overview status board(POSB) and digital indicator(DI) were designed and manufactured. The prototype advanced alarm system which employed the new alarm logics and algorithm compared with the conventional alarm system were developed and its effectiveness was proved. Optical communication system which has multi-drop feature and capability of upgrading to large-scale system by using BITBUS communication protocol which is proven technology, were developed. Reliability of that system was enhanced by using distributed control. (Author)

  17. State of work on Main Task 3.1.3 of Complex Programme of Scientific and Technical Progress and precondition for ensuring Czechoslovak automatic control system instrumentation and electrical parts for new-generation power plant project

    International Nuclear Information System (INIS)

    Hrebik, V.

    1990-01-01

    A brief account is given of the state of negotiations with the Soviet partner concerning the preparation, creation and implementation of prospective automated technological equipment control systems at WWER type nuclear power plants. The organization is very clumsy in some fields and their conceptions are not clear. (Z.S.)

  18. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Main report (Chapters 7--12). Volume 2, Part 1B

    International Nuclear Information System (INIS)

    Chu, T.L.; Musicki, Z.; Kohut, P.

    1994-06-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specific shutdown accidents would be useful

  19. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal fires during mid-loop operations. Volume 3, Part 1, Main report

    International Nuclear Information System (INIS)

    Musicki, Z.; Chu, T.L.; Yang, J.; Ho, V.; Hou, Y.M.; Lin, J.; Siu, N.

    1994-07-01

    During l989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than fun power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in ' the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few. procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful

  20. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Main report (Chapters 1--6). Volume 2, Part 1A

    International Nuclear Information System (INIS)

    Chu, T.L.; Musicki, Z.; Kohut, P.

    1992-06-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown written specifically for shutdown accidents would be useful. This document presents Chapters 1--6 of the report

  1. Small-scale hydro power plant on the main drinking water line La Rippaz in Bex, Switzerland - Feasibility study; Petite centrale hydraulique. Aduction d'eau potable La Rippaz. Etude de faisabilite

    Energy Technology Data Exchange (ETDEWEB)

    Chapallaz, J.-M. [Jean-Marc Chapallaz, Ingenieur EPFL/SIA, Baulmes (Switzerland); Meylan, D. [Perret-Gentil et Rey et Associes SA, Ingenieurs civils et Ingenieurs Conseil EPF/SIA, Lausanne (Switzerland)

    2008-04-15

    This report for the Swiss Federal Office of Energy (SFOE) is a feasibility study for the replacement work of the drinking-water supply line from the location of the spring water collection to a water reservoir belonging to the rock-salt mining company 'Hotel des Salines' in Bex, Switzerland. Built 1887 and following years this water supply system has already been designed for power generation as well. However, a 40 kW micro-scale turbine has only been installed 2005 in the lower part of the water supply system (hydraulic head: 115 m). The new project includes the replacement of the existing piping by a penstock, the construction of a new water collection reservoir at the highest point, the construction of a new 300 kW hydro power plant using the upper part of the water supply system (hydraulic head: 520 m), and some improvements of the existing lower power plant. The available water flow rate lies in the range 57-70 l/s, all the year round. The question arising is whether this construction project could be financed by the benefit from the sale of electricity that could be produced by the two power plants. The authors of the study estimate the power production to be 2.5 kWh/y. If the electricity can be sold at least at CHF 0.20/kWh for 25 years this could finance the whole project that has an estimated cost of CHF 7,000,000.

  2. Power Outages

    Science.gov (United States)

    ... Publications Emergency Alerts Preparedness Portal Preparedness Messaging Calendar Social Media Preparedness Toolkits Preparedness News Languages About Us Build a Kit Close Search Enter Search Term(s): Main Content Home Be Informed Power Outages Power Outages Extended power outages may impact ...

  3. Study of the beam-cavity interaction in the CERN PS 10 MHz cavities and investigation of hardware solutions to reduce beam loading

    CERN Document Server

    AUTHOR|(CDS)2086984; Palumbo, Luigi

    In the Proton Synchrotron (PS), where the LHC protons longitudinal structure (bunch spacing) is determined as the result of a sophisticated series of Radio Frequency (RF) gymnastics, collective effects were identified as a major limitation to the achievable beam current delivered to the LHC. Dedicated machine development studies pointed out the RF cavities to be one of the major source of instability in the PS. In particular, the 10 MHz RF system, responsible for beam acceleration, was identified as the most probable impedance source in the machine. The cavity impedance limits the circulating intensity in the accelerator since the beam-induced voltage could trigger longitudinal instabilities causing beam losses. For this reason the cavity impedance seen by the beam must be kept as low as possible. In the framework of the LHC Injector Upgrade (LIU) project, the present PS 10 MHz RF system requires an upgrade, in order to reach higher beam intensities and to reduce beam loading. This thesis focuses on the impro...

  4. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Evaluation of severe accident risk during mid-loop operations. Main report. Volume 6. Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Jo, J.; Lin, C.C.; Neymotin, L. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1995-05-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. A phased approach was used in the level-1 program. In phase 1 which was completed in Fall 1991, a coarse screening analysis including internal fire and flood was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The results of the phase 2 level 2/3 study are the subject of this volume of NUREG/CR-6144, Volume 6.

  5. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Evaluation of severe accident risk during mid-loop operations. Main report. Volume 6. Part 1

    International Nuclear Information System (INIS)

    Jo, J.; Lin, C.C.; Neymotin, L.

    1995-05-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. A phased approach was used in the level-1 program. In phase 1 which was completed in Fall 1991, a coarse screening analysis including internal fire and flood was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The results of the phase 2 level 2/3 study are the subject of this volume of NUREG/CR-6144, Volume 6

  6. Design of earth slide prevention structure and results of analyzing its behavior in excavation work for main building foundation for No.4 plant in Kashiwazaki-Kariwa Nuclear Power Station

    International Nuclear Information System (INIS)

    Kuroda, Teruo; Shimazu, Masaomi; Terada, Kenji

    1990-01-01

    In the construction works for No.4 plant in Kashiwazaki-Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc., the excavation work using ground anchor type earth slide prevention structure of about 30 m height intended for soft rocks was carried out. In this report, the outline of the design of the earth slide prevention structure is described, and based on the results of measurement of the earth slide prevention structure and surrounding ground during the period of the excavation work, the effect that the underground continuous wall normally intersecting with the back of the earth slide prevention wall and structurally separated from it exerted to the deformation behavior of the earth slide prevention wall was examined, and the results are reported. The geological features of the site are explained. The excavation work is to excavate the site of +5 m level down to -26 m for the turbine building and to -38.15 m for the reactor building, and the quantity of earth to be excavated is 1.39 million m 3 . These valuable experiences are utilized for the design and construction of the following plants. (K.I.)

  7. Enhancing training in the main control room

    International Nuclear Information System (INIS)

    McGuigan, K.; O'Leary, K.; Canavan, K.

    2004-01-01

    In 2003 Pickering B Nuclear of Ontario Power Generation installed a Desktop Simulator (DTS) in the Main Control Room (MCR) for training purposes. This paper will outline why this training enhancement was undertaken and the approach taken to secure its use in an active MCR environment while minimizing distractions to plant operations. (author)

  8. Main facts 1995; Faits marquants 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: new applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, monitoring and plants operations.

  9. D.E.R. 91 main facts

    International Nuclear Information System (INIS)

    Schmidt, N.

    1991-01-01

    This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: New applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, network analysis, information and informatic equipment

  10. D.E.R. 92 - Main facts

    International Nuclear Information System (INIS)

    1992-01-01

    This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: new applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, network analysis, information and informatic equipment

  11. Power program and nuclear power

    International Nuclear Information System (INIS)

    Chernilin, Yu.F.

    1990-01-01

    Main points of the USSR power program and the role of nuclear power in fuel and power complex of the country are considered. Data on dynamics of economic indices of electric power generation at nuclear power plants during 1980-1988 and forecasts till 2000 are presented. It is shown that real cost of 1 kW/h of electric power is equal to 1.3-1.8 cop., and total reduced cost is equal to 1.8-2.4 cop

  12. Maine's MOLLOCKET and METALLAK: Adherents of God's Secret Spirit Signal, SSS, Applied Physicists of the EMF/Manitou, Doctors, Reincarnationists, "Potlachers," Confidants of the Powerful, and, they Did Own the Land.

    Science.gov (United States)

    Andrade, Jennifer; Ferreira, Nadja; Mc Leod, Roger D.

    2007-04-01

    Northeastern ``Indians,'' reputed to ``make the weather,'' actually, from youth, observed earth phenomena, including SSS. These are subtle and barely detectable visual artifacts of the electromagnetic field, special information that led/leads to their spiritual belief in reincarnation, which came from the EMF/SSS communication, backward and forward, (up to) seven generations. It commands communal, democratic, ``potlatch'' redistribution of accumulated wealth, Mother Earth's bounty, from their land, gifted by ``The Great Spirit,'' Manitou, Peru's Ñari Huallac, ``Serpent God.'' Genetics established the non-Asian origins of 1/3 of North American Indians. Linguistics indicates a major impact westwards to us. MILLInocket is ``Adherent of God (Spirit-signal) monk Cathar.'' Katahdin, with a shared root, has Manitou. After 1820, Gov. E. Lincoln and at least one US senator went westward to MetALLAk; his biography is by a Rumford, ME Knight of Pythias. Why? MOLLOCKET frequently asserted ownership of western Maine. ``Great Council Fires,'' religious ``Law Things,'' were at Merrymeeting Bay in pre-Colonial times. ``Medicine men/priests'' often participated as their applied scientist-statesmen. To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2007.NES07.C2.1

  13. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - main report. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2), which is a boiling water reactor (BWR), located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low- level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  14. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - main report. Final report

    International Nuclear Information System (INIS)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System's Washington Nuclear Plant Two (WNP-2), which is a boiling water reactor (BWR), located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a open-quotes green fieldclose quotes condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low- level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined

  15. General design and main problems of a gas-heavy-water power reactor contained in a pressure vessel; Conception generale et principaux problemes d'un reacteur de puissance eau lourde-gaz contenu dans un caisson resistant

    Energy Technology Data Exchange (ETDEWEB)

    Roche, R; Gaudez, J C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    In the framework of research carried out on a CO{sub 2}-cooled power reactor moderated by heavy water, the so-called 'pressure vessel' solution involves the total integration of the core, of the primary circuit (exchanges and blowers) and of the fuel handling machine inside a single, strong, sealed vessel made of pre-stressed concrete. A vertical design has been chosen: the handling 'attic' is placed above the core, the exchanges being underneath. This solution makes it possible to standardize the type of reactor which is moderated by heavy-water or graphite and cooled by a downward stream of carbon dioxide gas; it has certain advantages and disadvantages with respect to the pressure tube solution and these are considered in detail in this report. Extrapolation presents in particular.problems due specifically to the heavy water (for example its cooling,its purification, the balancing of the pressures of the heavy water and of the gas, the assembling of the internal structures, the height of the attic, etc. (authors) [French] Dans le cadre des etudes d'un reacteur de puissance modere a l'eau lourde et refroidi-au gaz carbonique, la solution dite 'en caisson' consiste en une integration totale du coeur, du circuit primaire (echangeurs et soufflantes) et du dispositif de manutention du combustible a l'interieur d'un meme caisson etanche et resistant en beton precontraint. La disposition envisagee est verticale; le grenier de manutention est dispose au-dessus du coeur, les echangeurs en dessous. Cette solution, qui permet d'uniformiser les types de reacteurs moderes a l'eau lourde ou au graphite et refroidis par une circulation descendante de gaz carbonique presente, par rapport a la solution a tube de force, des avantages et des inconvenients qui sont analyses dans cette etude. L'extrapolation pose, en particulier, des problemes specifiques a l'eau lourde (tels que son refroidissement, son epuration, l'equilibrage des pression entre l'eau lourde et le gaz, le montage

  16. General design and main problems of a gas-heavy-water power reactor contained in a pressure vessel; Conception generale et principaux problemes d'un reacteur de puissance eau lourde-gaz contenu dans un caisson resistant

    Energy Technology Data Exchange (ETDEWEB)

    Roche, R.; Gaudez, J.C. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    In the framework of research carried out on a CO{sub 2}-cooled power reactor moderated by heavy water, the so-called 'pressure vessel' solution involves the total integration of the core, of the primary circuit (exchanges and blowers) and of the fuel handling machine inside a single, strong, sealed vessel made of pre-stressed concrete. A vertical design has been chosen: the handling 'attic' is placed above the core, the exchanges being underneath. This solution makes it possible to standardize the type of reactor which is moderated by heavy-water or graphite and cooled by a downward stream of carbon dioxide gas; it has certain advantages and disadvantages with respect to the pressure tube solution and these are considered in detail in this report. Extrapolation presents in particular.problems due specifically to the heavy water (for example its cooling,its purification, the balancing of the pressures of the heavy water and of the gas, the assembling of the internal structures, the height of the attic, etc. (authors) [French] Dans le cadre des etudes d'un reacteur de puissance modere a l'eau lourde et refroidi-au gaz carbonique, la solution dite 'en caisson' consiste en une integration totale du coeur, du circuit primaire (echangeurs et soufflantes) et du dispositif de manutention du combustible a l'interieur d'un meme caisson etanche et resistant en beton precontraint. La disposition envisagee est verticale; le grenier de manutention est dispose au-dessus du coeur, les echangeurs en dessous. Cette solution, qui permet d'uniformiser les types de reacteurs moderes a l'eau lourde ou au graphite et refroidis par une circulation descendante de gaz carbonique presente, par rapport a la solution a tube de force, des avantages et des inconvenients qui sont analyses dans cette etude. L'extrapolation pose, en particulier, des problemes specifiques a l'eau lourde (tels que son refroidissement, son epuration

  17. 77 FR 48565 - Maine Yankee Atomic Power Company, Maine Yankee Independent Spent Fuel Storage Installation...

    Science.gov (United States)

    2012-08-14

    ... reduction in a margin of safety nor creates a new or different kind of accident from any accident previously... the probability or consequences of an accident previously evaluated; (ii) granting the exemption would... would not result in a significant construction impact because there are no construction activities...

  18. Organization structure. Main activities of the Division

    International Nuclear Information System (INIS)

    2008-01-01

    In this chapter the organization structure as well as main activities of the Division for radiation safety, NPP decommissioning and radioactive waste management are presented. This Division of the VUJE, a.s. consists of the following sections and departments: Section for economic and technical services; Section for radiation protection of employees; Department for management of emergency situations and risk assessment; Department for implementation of nuclear power facilities decommissioning and RAW management; Department for personnel and environmental dosimetry; Department for preparation of NPP decommissioning; Department for RAW treatment technologies; Department for chemical regimes and physico-chemical analyses; Department for management of nuclear power facilities decommissioning and RAW management. Main activities of this Division are presented.

  19. Preliminary study for a micro-scale hydro power plant on the main drinking-water supply line connecting the municipal reservoir to the springs in Caviano, southern Switzerland; Realizzazione di una microcentrale idroelettrica sulla condotta di adduzione tra le captazioni delle sorgenti e il serbatoio di Caviano. Studio preliminare

    Energy Technology Data Exchange (ETDEWEB)

    Mutti, M.

    2008-01-15

    This report presents the comparative evaluation of two variants for the replacement/refurbishment work of the main drinking-water supply line from the location of the water collection to the water reservoirs of the community of Caviano, southern Switzerland. The question arising is whether this retrofitting work could be financed by the benefit from the sale of electricity that could be produced by a new micro-scale power plant foreseen on the supply line, to take advantage of the elevation difference of 445 m between water collection and water reservoir. From the technical point of view the project is feasible. The available water flow rate is nearly constant: about 5 l/s. The corresponding power of the electric generator would be 15 kW and the yearly power production 130,000 kWh. However, in the second variant, the power would be 9 kW and the production 80,000 kWh, as only 265 m elevation difference would be used for power generation. In this case, the upper part of the water supply line, which connects the water collection to an intermediate water reservoir supplying the upper hamlet of the community, would neither be used for power generation nor be retrofitted. According to Swiss regulations the generated electricity could be sold at CHF 0.30/kWh and CHF 0.34/kWh, respectively. In the first variant it is concluded that 76% of the total annual capital and maintenance cost for retrofitting work and power plant, CHF 52,000/y for 50 years, could be covered by electricity sales. The community would still have to finance CHF 13,000/y, compared to CHF 30,000/y if the power plant is not built. In the second variant the corresponding figures are 49% of the total of CHF 33,700/y, and CHF 6,400/y to additionally finance compared to CHF 15,400/y if the power plant is not built. However, in the second variant the community would anyway have to finance later on the retrofitting of the upper part of the water supply line.

  20. THE MATHEMATIC STIMULATION OF TRANSIENT PROCESS IN A.C. – SYSTEM “ELECTRIC-TRACTION NETWORK – LOCOMOTIVE” 3. SWITCHING ON MAIN POWER CONVERTER IN “FREE PLAY” MODE; THE ANALYSIS OF VOLTS AND CURRENTS IN THE POWER SUPPLY INPUT SYSTEM

    Directory of Open Access Journals (Sweden)

    T. M. Mischenko

    2011-05-01

    Full Text Available The article is a continuation of analysis of the electric equivalent AC circuit «traction substation − device of transversal compensation − electric-traction network − electric locomotive DS 3» and the influence on a power transformer in the idle mode, depending on the feeder voltage and the distance of an electric locomotive from a traction substation. The numeral calculations are performed and the voltage and current values in the electric power supply system are analyzed.

  1. THE MATHEMATIC STIMULATION OF TRANSIENT PROCESS IN A.C. – SYSTEM “ELECTRIC-TRACTION NETWORK – LOCOMOTIVE” 3. SWITCHING ON MAIN POWER CONVERTER IN “FREE PLAY” MODE; THE ANALYSIS OF VOLTS AND CURRENTS IN THE POWER SUPPLY INPUT SYSTEM

    OpenAIRE

    T. M. Mischenko

    2011-01-01

    The article is a continuation of analysis of the electric equivalent AC circuit «traction substation − device of transversal compensation − electric-traction network − electric locomotive DS 3» and the influence on a power transformer in the idle mode, depending on the feeder voltage and the distance of an electric locomotive from a traction substation. The numeral calculations are performed and the voltage and current values in the electric power supply system are analyzed.

  2. Mains protection. 4. ed.; Netzschutztechnik

    Energy Technology Data Exchange (ETDEWEB)

    Schossig, Thomas [Omicron Electronics GmbH, Klaus (Austria); Schossig, Walter

    2013-06-01

    Besides the description of the function of the line equipment, transformer protection functions and protection equipments, selective earth fault detection, voltage regulation, the control of the detuning information for the selection, commissioning and business management will be given. Special emphasis is put on a general adjustment standards and audit recommendations. Also transducers, auxiliary power supply and switching fault detection as well as classifications for equipment and circuit documents are mentioned. Updates affect particularly error clarification times, stimulation reliability, protection of SF6 switchgear, power directional frequency load shedding, protection of decentralized power plants, selective earth fault detection and communication in switch boards.

  3. Main terms of power economy. Pt. 4/8

    International Nuclear Information System (INIS)

    1975-01-01

    The Russian, Bulgarian, Hungarian, Polish, Romanian, Czech and German standardized versions of 67 terms relating to radioactive waste management and contamination as well as the corresponding definitions are listed. (author)

  4. Main results of the German nuclear power plant risk study

    International Nuclear Information System (INIS)

    Danzmann, H.J.

    1981-01-01

    The subject is discussed under the headings: introduction; purpose and task of the German risk study; approach; results of investigations (analyses of engineered plant features; determination of accident consequences); emergency response model; protective actions and countermeasures; evaluation. (U.K.)

  5. The advanced main control console for next japanese PWR plants

    International Nuclear Information System (INIS)

    Tsuchiya, A.; Ito, K.; Yokoyama, M.

    2001-01-01

    The purpose of the improvement of main control room designing in a nuclear power plant is to reduce operators' workload and potential human errors by offering a better working environment where operators can maximize their abilities. In order to satisfy such requirements, the design of main control board applied to Japanese Pressurized Water Reactor (PWR) type nuclear power plant has been continuously modified and improved. the Japanese Pressurized Water Reactor (PWR) Utilities (Electric Power Companies) and Mitsubishi Group have developed an advanced main control board (console) reflecting on the study of human factors, as well as using a state of the art electronics technology. In this report, we would like to introduce the configuration and features of the Advanced Main Control Console for the practical application to the next generation PWR type nuclear power plants including TOMARI No.3 Unit of Hokkaido Electric Power Co., Inc. (author)

  6. Diagnosing in building main pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Telegin, L.G.; Gorelov, A.S.; Kurepin, B.N.; Orekhov, V.I.; Vasil' yev, G.G.; Yakovlev, Ye. I.

    1984-01-01

    General principles are examined for technical diagnosis in building main pipelines. A technique is presented for diagnosis during construction, as well as diagnosis of the technical state of the pipeline-construction machines and mechanisms. The survey materials could be used to set up construction of main pipelines.

  7. Maine Agricultural Foods. Project SEED.

    Science.gov (United States)

    Beaulieu, Peter; Ossenfort, Pat

    This paper describes an activity-based program that teaches students in grades 4-12 about the importance of Maine agriculture in their lives. Specifically, the goal is to increase student awareness of how the foods they eat are planted, harvested, and processed. The emphasis is on crops grown in Maine such as potatoes, broccoli, peas, blueberries,…

  8. Main Propulsion Test Article (MPTA)

    Science.gov (United States)

    Snoddy, Cynthia

    2010-01-01

    Scope: The Main Propulsion Test Article integrated the main propulsion subsystem with the clustered Space Shuttle Main Engines, the External Tank and associated GSE. The test program consisted of cryogenic tanking tests and short- and long duration static firings including gimbaling and throttling. The test program was conducted on the S1-C test stand (Position B-2) at the National Space Technology Laboratories (NSTL)/Stennis Space Center. 3 tanking tests and 20 hot fire tests conducted between December 21 1 1977 and December 17, 1980 Configuration: The main propulsion test article consisted of the three space shuttle main engines, flightweight external tank, flightweight aft fuselage, interface section and a boilerplate mid/fwd fuselage truss structure.

  9. A Review of Power Electronics for Wind Power

    DEFF Research Database (Denmark)

    Chen, Zhe

    2011-01-01

    The paper reviews the power electronic applications for wind energy systems. Main wind turbine systems with different generators and power electronic converters are described. The electrical topologies of wind farms with power electronic conversion are discussed. Power electronic applications...

  10. Left main percutaneous coronary intervention.

    Science.gov (United States)

    Teirstein, Paul S; Price, Matthew J

    2012-10-23

    The introduction of drug-eluting stents and advances in catheter techniques have led to increasing acceptance of percutaneous coronary intervention (PCI) as a viable alternative to coronary artery bypass graft (CABG) for unprotected left main disease. Current guidelines state that it is reasonable to consider unprotected left main PCI in patients with low to intermediate anatomic complexity who are at increased surgical risk. Data from randomized trials involving patients who are candidates for either treatment strategy provide novel insight into the relative safety and efficacy of PCI for this lesion subset. Herein, we review the current data comparing PCI with CABG for left main disease, summarize recent guideline recommendations, and provide an update on technical considerations that may optimize clinical outcomes in left main PCI. Copyright © 2012 American College of Cardiology Foundation. Published by Elsevier Inc. All rights reserved.

  11. Guide to the Main Ring DO overpass

    International Nuclear Information System (INIS)

    Turkot, F.

    1985-01-01

    The DO overpass is a modification of the beam orbit in Main Ring in order to better accommodate a Tevatron collider detector at DO. The orbit is moved up approx. 51 inches over most of the long straight section at DO, thus making the Main Ring the world's first non-planar proton synchrotron. A similar overpass, but with four times the displacement, is planned for the CDF detector at the BO straight section. The nominal separation between the beam orbit in the Main Ring and the orbit in the Tevatron is 25.5 inches. Early in the design study of a detector that would utilize the Tevatron is a anti pp collider, it was apparent that a larger separation at the detector was highly desirable. In 1981, Tom Collins proposed a specific lattice geometry in the Main Ring for achieving larger separation, called ''the screw beam''. His proposal has served as the basis for the design of both the BO and DO overpasses. The main purpose of this report is to describe in some detail the implementation of the DO overpass. Topics to be covered include: (a) geometry of the overpass orbit, (b) the new hardware in the tunnel, (c) the power supply system, (d) the control facility, (e) accelerator beam dynamics ramifications, and (f) commissioning experience. A secondary purpose is to provide a fairly complete ''bibliography'' to the sources of information on the overpass. 17 refs., 17 figs

  12. Main: FEB3 [TP Atlas

    Lifescience Database Archive (English)

    Full Text Available nt to sterilization and rinsing - One of the main components of biofilms is polysaccharides - Some pit-formi...ng bacteria such as Sphingomonas species A1 possess superchannels that directly incorporate and decompose polysaccharides - Detai...e entrance of the superchannel have been elucidated - We have obtained the crystals of ABC importer complexe...of water pipes and dental plaque are examples of biofilms. One of the main components of biofilms is polysac

  13. PS main supply: motor-generator set.

    CERN Multimedia

    Maximilien Brice

    2002-01-01

    In picture 04 the motor is on the right in the background and the main view is of the generator. The peak power in each PS cycle drawn from the generator, up to 96 MW, is taken from the rotational kinetic energy of the rotor (a heavy-weight of 80 tons), which makes the rotational speed drop by only a few percent. The motor replenishes the average power of 2 to 4 MW. Photo 05: The motor-generator set is serviced every year and, in particular, bearings and slip-rings are carefully checked. To the left is the motor with its slip-rings visible. It has been detached from the axle and moved to the side, so that the rotor can be removed from the huge generator, looming at the right.

  14. New Main Ring control system

    International Nuclear Information System (INIS)

    Seino, K.; Anderson, L.; Ducar, R.; Franck, A.; Gomilar, J.; Hendricks, B.; Smedinghoff, J.

    1990-03-01

    The Fermilab Main Ring control system has been operational for over sixteen years. Aging and obsolescence of the equipment make the maintenance difficult. Since the advent of the Tevatron, considerable upgrades have been made to the controls of all the Fermilab accelerators except the Main Ring. Modernization of the equipment and standardization of the hardware and software have thus become inevitable. The Tevatron CAMAC serial system has been chosen as a basic foundation in order to make the Main Ring control system compatible with the rest of the accelerator complex. New hardware pieces including intelligent CAMAC modules have been designed to satisfy unique requirements. Fiber optic cable and repeaters have been installed in order to accommodate new channel requirements onto the already saturated communication medium system. 8 refs., 2 figs

  15. Challenges of the ILC Main Linac

    International Nuclear Information System (INIS)

    Ross, Marc

    2007-01-01

    With the completion of the ILC Reference Design Report (RDR), we begin the next phase of the project - development of the Engineering Design. Our strategy and priorities come from the identification, contained in the RDR, of scientific and engineering challenges of the ILC. First among these is the cost of the main linac which, including the associated earthworks and cooling/power systems, amounts to 60% of the ILC total cost. Next is the challenge to reach the highest practical gradient since this R and D has the largest cost leverage of any of the ongoing programs. Finally, we have to understand the beam dynamics and beam tuning processes in the main linac, as we will not have the opportunity to do full (or even large) scale tests of these before the linac is constructed.

  16. Main: FBB2 [TP Atlas

    Lifescience Database Archive (English)

    Full Text Available ion of the c-ring - A subunit packing model of E. coli c-ring has been proposed - The main chain secondary s...tructure of thermophile c-ring has been obtained ATP synthase is a general term for an enzyme that can synth

  17. Main: FEA5 [TP Atlas

    Lifescience Database Archive (English)

    Full Text Available al or an anti-cancer drug, is the main cause of hospital-acquired infection - Dru...e will elucidate the entire structure of the transport machinery in action to understand its functions in detail. FEA5.csml ...

  18. Residential Energy Efficiency Potential: Maine

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Eric J [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-11-02

    Energy used by Maine single-family homes that can be saved through cost-effective improvements. Prepared by Eric Wilson and Noel Merket, NREL, and Erin Boyd, U.S. Department of Energy Office of Energy Policy and Systems Analysis.

  19. CENTRE OF THE MAIN INTERESTS

    Directory of Open Access Journals (Sweden)

    DIANA DELEANU

    2013-05-01

    Full Text Available The centre of the main interests of the debtor is a legal tool meant to settle conflicts that can arise between jurisdictions in cross-border insolvencies, based on the principles of mutual recognition and co-operation.

  20. Pulsed power

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The key element of our pulsed power program is concentration of power in time and space by suppression of breakdown in dielectrics and in vacuum. Magnetically insulated vacuum transmission lines and magnetic suppression of insulator flashover have continued as the main reserch directions. Vacuum insulated line studies at Physics International have been expanded and a test bed at Sandia, called MITE (Magnetically Insulated Transmission Experiment), is under development. The choice for the baseline EBFA design will depend on the outcome of these studies and should be made in July 1977. The slow and intermediate speed pulsed power approaches to EBFA will be based on Proto I and Proto II results and several of the projected EBFA subsystems are presently being tested in Proto II. A further stage of power concentration, within the vacuum diode itself, would considerably ease the burden on dielectrics; methods of power multiplication involving magnetically imploded plasmas are being considered and tests have begun using the Ripple III apparatus

  1. ONKALO - Main drawings in 2007

    International Nuclear Information System (INIS)

    2008-05-01

    The first overall site characterisation programme for a Finnish repository of spent nuclear fuel was introduced in 1982. This programme already suggested that the site confirmation for a detailed repository design and safety assessment should include characterisation performed in an underground rock characterisation facility (URCF). This idea was confirmed during the detailed site characterisation. International views have also emphasised the importance of underground characterisation before the final decision to construct the repository is taken. The underground rock characterisation facility (ONKALO) is excavated at Olkiluoto in the municipality of Eurajoki. ONKALO should be constructed to allow characterisation work for site confirmation without jeopardising long-term safety of the repository site. It should also be possible to link ONKALO later to the repository as to a part of it. The construction of ONKALO was started in 2004 and will be completed in 2014. The characterisation work has started in ONKALO and will focus on the disposal depth. In the main drawings stage, ONKALO was described at the level of detail needed for a construction permit in 2003. This meant description of the location, final structures and final systems. This summary report describes the development of design to updated main drawings in 2007 at the same level of detail (no temporary arrangements are described). The main changes are the added exhaust air shaft and advancing the controlled area's inlet air shaft to the ONKALO phase. Also the layout and the depth of the characterisation levels have been updated according to the current bedrock information. Some buildings on the surface will house sets of equipment directly connected with underground facility and this equipment is described in this report. No buildings or other equipment are described in this report, because they are not directly connected with the underground facility. The main element of ONKALO is a system of

  2. A main sequence for quasars

    Science.gov (United States)

    Marziani, Paola; Dultzin, Deborah; Sulentic, Jack W.; Del Olmo, Ascensión; Negrete, C. A.; Martínez-Aldama, Mary L.; D'Onofrio, Mauro; Bon, Edi; Bon, Natasa; Stirpe, Giovanna M.

    2018-03-01

    The last 25 years saw a major step forward in the analysis of optical and UV spectroscopic data of large quasar samples. Multivariate statistical approaches have led to the definition of systematic trends in observational properties that are the basis of physical and dynamical modeling of quasar structure. We discuss the empirical correlates of the so-called “main sequence” associated with the quasar Eigenvector 1, its governing physical parameters and several implications on our view of the quasar structure, as well as some luminosity effects associated with the virialized component of the line emitting regions. We also briefly discuss quasars in a segment of the main sequence that includes the strongest FeII emitters. These sources show a small dispersion around a well-defined Eddington ratio value, a property which makes them potential Eddington standard candles.

  3. A Main Sequence for Quasars

    Directory of Open Access Journals (Sweden)

    Paola Marziani

    2018-03-01

    Full Text Available The last 25 years saw a major step forward in the analysis of optical and UV spectroscopic data of large quasar samples. Multivariate statistical approaches have led to the definition of systematic trends in observational properties that are the basis of physical and dynamical modeling of quasar structure. We discuss the empirical correlates of the so-called “main sequence” associated with the quasar Eigenvector 1, its governing physical parameters and several implications on our view of the quasar structure, as well as some luminosity effects associated with the virialized component of the line emitting regions. We also briefly discuss quasars in a segment of the main sequence that includes the strongest FeII emitters. These sources show a small dispersion around a well-defined Eddington ratio value, a property which makes them potential Eddington standard candles.

  4. At ISR Main Control Room

    CERN Multimedia

    1983-01-01

    After 13 years the exploitation of the Intersecting Storage Rings as a beam-beam collider went to an end. In this last year the demands were very exacting, both in terms of operating time and diversified running conditions (Annual Report 1983 p. 123). Before dismantelement the photographer made a last tour, see photos 8310889X --> 8310667X. This photo shows the Main Control Room.

  5. Alternative Fuels Data Center: Maine Transportation Data for Alternative

    Science.gov (United States)

    Biodiesel-Blended Diesel Documentation Requirement Data Download Fueling Stations 149 stations in Maine with alternative fuels Fuel Public Private Biodiesel (B20 and above) 2 1 Compressed Natural Gas (CNG) 0 2 Electric ://www.youtube.com/embed/jHftlruFR40 Video thumbnail for Maine's Only Biodiesel Manufacturer Powers Fleets in the

  6. Fermilab main accelerator quadrupole transistorized regulators for improved tune stability

    International Nuclear Information System (INIS)

    Yarema, R.J.; Pfeffer, H.

    1977-01-01

    During early operation of the Fermilab Main Accelerator, tune fluctuations, caused by the SCR-controlled power supplies in the quad bus, limited the beam aperature at low energies. To correct this problem, two transistorized power supplies were built in 1975 to regulate and filter the main ring quad magnet current during injection and beam acceleration through the rf transistion region. There is one power supply in series with each quad bus. Each supply uses 320 parallel power transistors and is rated at 300A, 120V. Since the voltage and current capabilities of the transistorized supplies are limited, the supplies are turned-off at about 25GeV. A real-time computer system initiates turn-on of the SCR-controlled power supplies and regulation takeover by the SCR-controlled supplies, at the appropriate times

  7. JWST-MIRI spectrometer main optics design and main results

    Science.gov (United States)

    Navarro, Ramón; Schoenmaker, Ton; Kroes, Gabby; Oudenhuysen, Ad; Jager, Rieks; Venema, Lars

    2017-11-01

    MIRI ('Mid InfraRed Instrument') is the combined imager and integral field spectrometer for the 5-29 micron wavelength range under development for the James Webb Space Telescope JWST. The flight acceptance tests of the Spectrometer Main Optics flight models (SMO), part of the MIRI spectrometer, are completed in the summer of 2008 and the system is delivered to the MIRI-JWST consortium. The two SMO arms contain 14 mirrors and form the MIRI optical system together with 12 selectable gratings on grating wheels. The entire system operates at a temperature of 7 Kelvin and is designed on the basis of a 'no adjustments' philosophy. This means that the optical alignment precision depends strongly on the design, tolerance analysis and detailed knowledge of the manufacturing process. Because in principle no corrections are needed after assembly, continuous tracking of the alignment performance during the design and manufacturing phases is important. The flight hardware is inspected with respect to performance parameters like alignment and image quality. The stability of these parameters is investigated after exposure to various vibration levels and successive cryogenic cool downs. This paper describes the philosophy behind the acceptance tests, the chosen test strategy and reports the results of these tests. In addition the paper covers the design of the optical test setup, focusing on the simulation of the optical interfaces of the SMO. Also the relation to the SMO qualification and verification program is addressed.

  8. Main ring transition crossing simulations

    International Nuclear Information System (INIS)

    Kourbanis, I.; Ng, King-Yuen.

    1990-10-01

    We used ESME to simulate transition crossing in the Main Ring (MR). For the simulations, we followed the MR 29 cycle used currently for bar p production with a flat top of 120 GeV. In Sect. II, some inputs are discussed. In Sect. III, we present simulations with space charge turned off so that the effect of nonlinearity can be studied independently. When space charge is turned on in Sect. IV, we are faced with the problem of statistical errors due to binning, an analysis of which is given in the Appendices. Finally in Sects. V and VI, the results of simulations with space charge are presented and compared with the experimental measurements. 7 refs., 6 figs

  9. The role of Main Institutions

    DEFF Research Database (Denmark)

    Persson, H Thomas R; Chabanet, Didier; Rakar, Fredrik

    2017-01-01

    ), in many countries the need emerged to understand the best methods to promote their establishment and continued success. In order to understand these issues, to contribute to the academic debate on SEs and to give useful policy advice on a truly enabling ecosystem, in November 2013 a consortium of 11...... Entrepreneurship”; to identify the “New Generation” of Social Entrepreneurs; to build an “Evolutionary Theory of Social Entrepreneurship”; to provide effective policy advices to stakeholders. In order to pursue and achieve these research objectives, the consortium implemented a complex research design...... in the social economy; - In the fifth chapter the authors address the role of the main institutions in developing (or hindering) social enterprises; - In the sixth chapter, stakeholder network maps are used to identify four ‘ecosystem types’ across the 10 partner countries; - The seventh chapter gives...

  10. Main injector synchronous timing system

    International Nuclear Information System (INIS)

    Blokland, W.; Steimel, J.

    1998-01-01

    The Synchronous Timing System is designed to provide sub-nanosecond timing to instrumentation during the acceleration of particles in the Main Injector. Increased energy of the beam particles leads to a small but significant increase in speed, reducing the time it takes to complete a full turn of the ring by 61 nanoseconds (or more than 3 rf buckets). In contrast, the reference signal, used to trigger instrumentation and transmitted over a cable, has a constant group delay. This difference leads to a phase slip during the ramp and prevents instrumentation such as dampers from properly operating without additional measures. The Synchronous Timing System corrects for this phase slip as well as signal propagation time changes due to temperature variations. A module at the LLRF system uses a 1.2 Gbit/s G-Link chip to transmit the rf clock and digital data (e.g. the current frequency) over a single mode fiber around the ring. Fiber optic couplers at service buildings split off part of this signal for a local module which reconstructs a synchronous beam reference signal. This paper describes the background, design and expected performance of the Synchronous Timing System. copyright 1998 American Institute of Physics

  11. Main injector synchronous timing system

    International Nuclear Information System (INIS)

    Blokland, Willem; Steimel, James

    1998-01-01

    The Synchronous Timing System is designed to provide sub-nanosecond timing to instrumentation during the acceleration of particles in the Main Injector. Increased energy of the beam particles leads to a small but significant increase in speed, reducing the time it takes to complete a full turn of the ring by 61 nanoseconds (or more than 3 rf buckets). In contrast, the reference signal, used to trigger instrumentation and transmitted over a cable, has a constant group delay. This difference leads to a phase slip during the ramp and prevents instrumentation such as dampers from properly operating without additional measures. The Synchronous Timing System corrects for this phase slip as well as signal propagation time changes due to temperature variations. A module at the LLRF system uses a 1.2 Gbit/s G-Link chip to transmit the rf clock and digital data (e.g. the current frequency) over a single mode fiber around the ring. Fiber optic couplers at service buildings split off part of this signal for a local module which reconstructs a synchronous beam reference signal. This paper describes the background, design and expected performance of the Synchronous Timing System

  12. Main technical topics in 1999

    International Nuclear Information System (INIS)

    2000-01-01

    This Safety Authority annual report strives to present current organizational provisions and future trends in nuclear safety supervision in France and to describe the most outstanding occurrences during the past year. A first part presents nine documents concerning the main topics of 1999: aging of nuclear installations, the Offsite Emergency Plans (PPI), the impact of nuclear activities on man and the environment, the criticality hazards, EDF in 1999, the EPR project, the Andra in 1999, the transport incidents, the nuclear safety in eastern Europe. The second part presents the missions and actions of the Nuclear Installations Safety in the domains of the liabilities, the organization of the nuclear safety control, the regulations of the INB, the public information, the international relations, the crisis management, the radioactive materials transportation, the radioactive wastes. The equipment, the radiation protection and the exploitation of the pressurized water reactors are also treated just as the experimental reactors, the fuel cycle installations and the the nuclear installations dismantling. (A.L.B.)

  13. Main challenges of residential areas

    Directory of Open Access Journals (Sweden)

    Oana Luca

    2017-06-01

    Full Text Available The present article is a position paper aiming to initiate a professional debate related to the aspects related to the urban dysfunctions leading to the wear of the residential areas. The paper proposes a definition of the wear process, identify the main causes leading to its occurrence and propose a number of solutions to neutralise the dysfunctions. The three wearing phases of residential areas components are emphasized, exploring their lifecycle. In order to perform the study of urban wear, the status of the residential areas components can be established and monitored, and also the variables of the function that can mathematically model the specific wear process may be considered. The paper is considered a first step for the model adjustment, to be tested and validated in the following steps. Based on the mathematical method and model, there can be created, in a potential future research, the possibility of determining the precarity degree for residential areas/neighbourhoods and cities, by minimising the subjective component of the analyses preceding the decision for renovation or regeneration.

  14. Research in auditing: main themes

    Directory of Open Access Journals (Sweden)

    Marcelo Porte

    Full Text Available ABSTRACT The passage of the Sarbanes-Oxley Act (SOX was a turning point in auditing and in auditors practice for the academic world. Research concerning the characterization of academic production related to auditing is in its third decade. Its analysis is accomplished by means of definition of keywords, abstracts or title, and information on thematic association within the academic production itself in auditing is undisclosed. In order to revise this gap in auditing literature, this study identified the main themes in auditing and their association in post-SOX era by analyzing the content of objectives and hypothesis of 1,650 publications in Web of Science (2002-2014. The findings in this study extended those from the study by Lesage and Wechtler (2012 from 16 auditing thematic typologies to 22. The results demonstrate that the themes audit report & financial statement users, corporate governance, audit market, external audit, socio-economic data of the company, international regulation, and fraud risk & audit risk were the most addressed in the publications about auditing. Corporate governance has a broader association with the other themes in the area. Future researches may use these themes and relate them to the methodologies applied to audit studies.

  15. Operation Aspect of the Main Control Room of NPP

    International Nuclear Information System (INIS)

    Sahala M Lumbanraja

    2009-01-01

    The main control room of Nuclear Power Plant (NPP) is operational centre to control all of the operation activity of NPP. NPP must be operated carefully and safely. Many aspect that contributed to operation of NPP, such as man power whose operated, technology type used, ergonomic of main control room, operational management, etc. The disturbances of communication in control room must be anticipated so the high availability of NPP can be achieved. The ergonomic of the NPP control room that will be used in Indonesia must be designed suitable to anthropometric of Indonesia society. (author)

  16. A Review of Power Electronics for Wind Power

    Institute of Scientific and Technical Information of China (English)

    Zhe CHEN

    2011-01-01

    The paper reviews the power electronic applications for wind energy systems.Main wind turbine systems with different generators and power electronic converters are described.The electrical topologies of wind farms with power electronic conversion are discussed.Power electronic applications for improving the performance of wind turbines and wind farms in power systems have been illustrated.

  17. Channel separation using the transversity parameter in the pi /sup +/n to p pi /sup +/ pi /sup -/ reaction at 9 GeV/c

    CERN Document Server

    Armenise, N

    1978-01-01

    To solve the problem of separating competitive channels in a multiparticle final state the use of a parameter, called A(*), measuring the 'event transversity' has been suggested. The A parameter is found to be as powerful as prism plot analysis in separating different channels and economic with respect to the computer time. The transversity method is applied to the three-body reaction p/sup +/n to p pi /sup +/ pi /sup -/ at 9 TeV/c selected in pi /sup +/d interactions obtained in 2m-DBC exposed at CERN-PS. The main contributions in the final state are rho /sup 0/, f, g/sup 0/ (a dipion mass resonance) resonance production and neutron diffraction dissociation. (5 refs).

  18. Main tendencies meeting future energy demands

    International Nuclear Information System (INIS)

    Flach, G.; Riesner, W.; Ufer, D.

    1989-09-01

    The economic development in the German Democratic Republic within the preceding 10 years has proved that future stable economic growth of about 4 to 4.5% per annum is only achievable by ways including methods of saving resources. This requires due to the close interdependences between the social development and the level of the development in the energy sector long-term growth rates of the national income of 4 to 4.5% per annum at primary energy growth rates of less than 1% per annum. It comprises three main tendencies: 1. Organization of a system with scientific-technical, technological, economic structural-political and educational measures ensuring in the long term less increase of the energy demand while keeping the economic growth at a constant level. 2. The long-term moderate extension and modernization of the GDR's energy basis is characterized by continuing use of the indigenous brown coal resources for the existing power plant capacities and for district heating. 3. The use of modern and safe nuclear power technologies defines a new and in future more and more important element of the energy basis. Currently about 10% of electricity in the GDR are covered by nuclear energy, in 2000 it will be one third, after 2000 the growth process will continue. The experience shows: If conditions of deepened scientific consideration of all technological processes and the use of modern diagnosis and computer technologies as well as permanent improvement of the safety-technological components and equipment are guaranteed an increasing use of such systems for the production of electricity and heat is socially acceptable. Ensuring a high level of education and technical training of everyone employed in the nuclear energy industry, strict safety restrictions and independent governmental control of these restrictions are important preconditions for the further development in this field. 3 refs, 5 tabs

  19. Wind power in modern power systems

    DEFF Research Database (Denmark)

    Chen, Zhe

    2013-01-01

    In recent years, wind power is experiencing a rapid growth, and large-scale wind turbines/wind farms have been developed and connected to power systems. However, the traditional power system generation units are centralized located synchronous generators with different characteristics compared...... with wind turbines. This paper presents an overview of the issues about integrating large-scale wind power plants into modern power systems. Firstly, grid codes are introduced. Then, the main technical problems and challenges are presented. Finally, some possible technical solutions are discussed....

  20. Radio frequency systems for present and future accelerators

    International Nuclear Information System (INIS)

    Raka, E.C.

    1987-01-01

    Rf systems are described for the FNAL Main Ring and Tevatron Ring, CERN SPS and LEP, and HERA proton acceleration system, CERN PS e + e/sup minus/ acceleration system, and CERN EPA monochromatic cavity. Low impedance rf systems in CERN ISR, the Brookhaven CBA, and SSC are also discussed

  1. Power generation by nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.

    2004-01-01

    Nuclear power plays an important role in the world, European (33%) and French (75%) power generation. This article aims at presenting in a synthetic way the main reactor types with their respective advantages with respect to the objectives foreseen (power generation, resources valorization, waste management). It makes a fast review of 50 years of nuclear development, thanks to which the nuclear industry has become one of the safest and less environmentally harmful industry which allows to produce low cost electricity: 1 - simplified description of a nuclear power generation plant: nuclear reactor, heat transfer system, power generation system, interface with the power distribution grid; 2 - first historical developments of nuclear power; 3 - industrial development and experience feedback (1965-1995): water reactors (PWR, BWR, Candu), RBMK, fast neutron reactors, high temperature demonstration reactors, costs of industrial reactors; 4 - service life of nuclear power plants and replacement: technical, regulatory and economical lifetime, problems linked with the replacement; 5 - conclusion. (J.S.)

  2. Tinkering at the main-ring lattice

    Energy Technology Data Exchange (ETDEWEB)

    Ohnuma, S.

    1982-08-23

    To improve production of usable antiprotons using the proton beam from the main ring and the lossless injection of cooled antiprotons into the main ring, modifications of the main ring lattice are recommended.

  3. Main attributes influencing spent nuclear fuel management

    International Nuclear Information System (INIS)

    Andreescu, N.; Ohai, D.

    1997-01-01

    All activities regarding nuclear fuel, following its discharge from the NPP, constitute the spent fuel management and are grouped in two possible back end variants, namely reprocessing (including HLW vitrification and geological disposal) and direct disposal of spent fuel. In order to select the appropriate variant it is necessary to analyse the aggregate fulfillment of the imposed requirements, particularly of the derived attributes, defined as distinguishing characteristics of the factors used in the decision making process. The main identified attributes are the following: - environmental impact, - availability of suitable sites, - non-proliferation degree, -strategy of energy, - technological complexity and technical maturity, -possible further technical improvements, - size of nuclear programme, - total costs, - public acceptance, - peculiarity of CANDU fuel. The significance of the attributes in the Romanian case, taking into consideration the present situation, as a low scenario and a high scenario corresponding to an important development of the nuclear power, after the year 2010, is presented. According to their importance the ranking of attributes is proposed . Subsequently, the ranking could be used for adequate weighing of attributes in order to realize a multi-criteria analysis and a relevant comparison of back end variants. (authors)

  4. EPR compared to international requirements (Mainly EUR)

    International Nuclear Information System (INIS)

    Broecker, B.

    1996-01-01

    A number of European Utilities have entered an agreement to write common requirements dedicated to future light water nuclear power plants to be built in Europe. The activities are known under the sign EUR (European Utilities Requirements). EPR, the future European Pressurized water Reactor, is the first installation of this type which will be operational from the year 2000 onwards, must fulfill the European requirements. EPR will serve as a test whether these requirements are realistic and well balanced. At the basic design stage of EPR, this paper concentrates on four main topics: the requirements which are new compared with existing reactors and which put a major challenge to the designer; the requirements today still open and the way they can be met by the EPR or not; the points for which already today the EPR special requirements exceed the EUR; the examples where the design of the EPR has given feedback which has led to a change of the EUR. EPR and EUR are different approaches to the reactor of the future. EUR is a set of requirements which leaves a flexibility to the designer while EPR is a real project which defines the technical solutions. EPR will fulfill the EUR and will at the same time serve as a test whether these requirements are realistic. EPR will also fulfill international requirements with minor changes. (J.S.). 7 figs

  5. Prototype fast breeder reactor main options

    International Nuclear Information System (INIS)

    Bhoje, S.B.; Chellapandi, P.

    1996-01-01

    Fast reactor programme gets importance in the Indian energy market because of continuous growing demand of electricity and resources limited to only coal and FBR. India started its fast reactor programme with the construction of 40 MWt Fast Breeder Test Reactor (FBTR). The reactor attained its first criticality in October 1985. The reactor power will be raised to 40 MWt in near future. As a logical follow-up of FBTR, it was decided to build a prototype fast breeder reactor, PFBR. Considering significant effects of capital cost and construction period on economy, systematic efforts are made to reduce the same. The number of primary and secondary sodium loops and components have been reduced. Sodium coolant, pool type concept, oxide fuel, 20% CW D9, SS 316 LN and modified 9Cr-1Mo steel (T91) materials have been selected for PFBR. Based on the operating experience, the integrity of the high temperature components including fuel and cost optimization aspects, the plant temperatures are recommended. Steam temperature of 763 K at 16.6 MPa and a single TG of 500 MWe gross output have been decided. PFBR will be located at Kalpakkam site on the coast of Bay of Bengal. The plant life is designed for 30 y and 75% load factor. In this paper the justifications for the main options chosen are given in brief. (author). 2 figs, 2 tabs

  6. Study of the main mechanisms for incentive alternative sources of renewable energy for power generation in Chile, Argentina and Brazil; Estudo dos principais mecanismos de incentivo as fontes alternativas de energia para geracao renovavel de eletricidade no Chile, Argentina e Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Nogueira, Larissa Goncalves [Universidade Estadual de Campinas (FEM/UNICAMP), SP (Brazil). Fac. de Engenharia Mecanica. Dept. de Energia; Dedecca, Joao Gorestein; Jannuzzi, Gilberto de Martinno; Gomes, Rodolfo Dourado [Universidade Estadual de Campinas (UNICAMP), SP (Brazil)

    2010-07-01

    From the experience of developed countries, Brazil, Chile and Argentina are implementing some important mechanisms for encouraging alternative sources of renewable energy for power generation and thus manage to incorporate these power sources in their power matrix. However, the obstacles faced are not insignificant. This study will present and analyze the Chilean, Argentinean and Brazilian experience when it comes to implementing programs and policies based on feed-in tariffs, renewable portfolio standard and bidding mechanisms. (author)

  7. D.E.R. 85: main facts

    International Nuclear Information System (INIS)

    1986-01-01

    This report presents the important facts among the studies carried out by the ''Direction des Etudes et Recherches'' (E.D.F.): new applications of electric power for customers, protection of environment, classical equipments for power plants and nuclear equipments, monitoring and control of power plants, electrical equipments, development and operation of electrical networks, informatics and office automation [fr

  8. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1976-01-01

    The invention concerns a quick-acting valve on the main-steam pipe of a nuclear power plant. The engineering design of the valve is to be improved. To the main valve disc, a piston-operated auxiliary valve disc is to be assigned closing a section of the area of the main valve disc. This way it is avoided that the drive of the main valve disc has to carry out different movements. 15 sub-claims. (UWI) [de

  9. 75 FR 27863 - Savings Bank of Maine, MHC and Savings Bank of Maine, Gardiner, Maine; Approval of Conversion...

    Science.gov (United States)

    2010-05-18

    ... DEPARTMENT OF THE TREASURY Office of Thrift Supervision [AC-38: OTS Nos. 06947 and H 4709] Savings Bank of Maine, MHC and Savings Bank of Maine, Gardiner, Maine; Approval of Conversion Application Notice is hereby given that on May 7, 2010, the Office of Thrift Supervision approved the application of...

  10. Main cycle controls for the AGS Booster synchrotron

    International Nuclear Information System (INIS)

    Culwick, B.B.; Yen, S.

    1991-01-01

    The AGS Booster is a separated function synchrotron with the main excitation coils of the dipoles and quadrupoles connected electrically in series. This circuit is driven by a complex modular power supply with current and voltage reference functions to obtain the desired magnetic fields as a function of time. The dipole cycle is defined by algebraic functions specifying the desired field profile as a function of time. These functions are processed through successive phases to convert to the signals needed to provide the power supply with one current and six voltage references. The user interface and algorithms to derive the control variables are described. 4 refs., 3 figs

  11. NTD Silicon; Product Characteristics, Main Uses and Growth Potential

    International Nuclear Information System (INIS)

    Hansen, M. G.; Bjorling, C. F.

    2013-01-01

    Topsil is a specialised manufacturer of ultrapure float zone silicon since 1959, headquartered in Denmark. Topsil co-pioneered the invention of Neutron Transmutation Doped (NTD) monocrystalline silicon with research institute Risoe in the 1970s and has since then been world leading manufacturer of NTD silicon for the power market. This presentation will focus on NTD silicon; its characteristics, invention and main uses. It will address the trends of the power market and market projections for NTD, and discuss the growth potential in the years ahead, including larger silicon wafers and management of the NTD supply chain

  12. NTD Silicon; Product Characteristics, Main Uses and Growth Potential

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, M. G.; Bjorling, C. F. [Topsil Semiconductor Materials A/S, Odense (Denmark)

    2013-07-01

    Topsil is a specialised manufacturer of ultrapure float zone silicon since 1959, headquartered in Denmark. Topsil co-pioneered the invention of Neutron Transmutation Doped (NTD) monocrystalline silicon with research institute Risoe in the 1970s and has since then been world leading manufacturer of NTD silicon for the power market. This presentation will focus on NTD silicon; its characteristics, invention and main uses. It will address the trends of the power market and market projections for NTD, and discuss the growth potential in the years ahead, including larger silicon wafers and management of the NTD supply chain.

  13. Solar thermal power and photovoltaic energy are both developing; Solaire a concentration et solaire photovoltaique: la main dans la main

    Energy Technology Data Exchange (ETDEWEB)

    Le Jannic, N.; Houot, G.

    2010-11-15

    Thermodynamic solar energy and photovoltaic energy are expected to reach together a quarter of the world electricity production by 2050. In France the development of thermodynamic solar plants is hampered by the high cost of land in the sunny regions. As for photovoltaic energy, France has the potentiality to become an important producer. Since 2006, the French government has supported photovoltaic energy by proposing incentive electricity purchase prices guaranteed for 20 years. In 2006, the Ines research institute was founded, one of its research fields is the development of high yield silicon cells. (A.C.)

  14. Electric power conservation in Brazil

    International Nuclear Information System (INIS)

    Hollanda, J.B. de

    1989-01-01

    The Brazilian Electric Power Conservation Program (PROCEL) is discussed. The main objective of this program is the optimization of electric power use, including consideration about prices, technology development and legislation. (M.V.M.)

  15. Nuclear power: pros and cons

    International Nuclear Information System (INIS)

    Hirsch, H.

    1977-01-01

    The author deals with the nuclear power controversy in science and indicates the main points of the nuclear power debate by the population. The different scientific and ideological positions shown by the results of the campaign are explained. (HP) [de

  16. 30 CFR 57.6160 - Main facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Main facilities. 57.6160 Section 57.6160...-Underground Only § 57.6160 Main facilities. (a) Main facilities used to store explosive material underground... facilities will not prevent escape from the mine, or cause detonation of the contents of another storage...

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

    International Nuclear Information System (INIS)

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

    1994-06-01

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

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

    International Nuclear Information System (INIS)

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

    1994-06-01

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

  19. Power without Glory

    DEFF Research Database (Denmark)

    Jørgensen, Kenneth Mølbjerg

    This book is about power and language in organizations. Its purpose is, more specifically, to develop and apply a method for exploring power in organizations where organizations are conceptualized by drawing on Wittgenstein’s concept of language games. The method is genealogy and is closely linked...... to Foucault’s conception of power. The book is written with one main purpose—to highlight some aspects of Foucault’s conception of power that, in my opinion, are not sufficiently explored in extant organization studies: Genealogy and the practices of power....

  20. Isolators Including Main Spring Linear Guide Systems

    Science.gov (United States)

    Goold, Ryan (Inventor); Buchele, Paul (Inventor); Hindle, Timothy (Inventor); Ruebsamen, Dale Thomas (Inventor)

    2017-01-01

    Embodiments of isolators, such as three parameter isolators, including a main spring linear guide system are provided. In one embodiment, the isolator includes first and second opposing end portions, a main spring mechanically coupled between the first and second end portions, and a linear guide system extending from the first end portion, across the main spring, and toward the second end portion. The linear guide system expands and contracts in conjunction with deflection of the main spring along the working axis, while restricting displacement and rotation of the main spring along first and second axes orthogonal to the working axis.

  1. Pilot RCM application to the Diablo Canyon main stream system

    International Nuclear Information System (INIS)

    Groff, C.R.; Beckham, P.E.; Bych, K.H.

    1988-01-01

    In 1986 Pacific Gas ampersand Electric Company (PG ampersand E) became extremely interested in reliability-centered maintenance (RCM) after the initial review of two successful Electric Power Research Institute sponsored projects. RCM was visualized as a methodology to common sensitize the burgeoning preventive maintenance (PM) program at the Diablo Canyon plant. RCM could further the uses of predictive and condition-monitoring techniques, as well as eliminate maintenance on components whose failures were noncritical. An extensive review of maintenance and operation experience data, in conjunction with plant staff recommendations and a prioritization according to maintenance expenditures and operational/safety significance, produced the selected system: the turbine main steam supply system (main steam). The pilot project segmented the main steam system into eight subsystems to aid in analysis: (a) main steam isolation valves, (b) auxiliary feedwater pump turbine, (c) overpressure protection (steam dump), (d) main feedwater pump turbines, (e) main steam, (f) main turbine, (g) steam blowdown, and (h) moisture separator reheaters. System analysis activities, including the preparation of functional failure analyses, failure modes and effects analyses, and logic model analyses, were conducted in parallel with corrective and preventive maintenance data-gathering activities to maximize project team personnel participation during the project. Results and lessons learned are summarized

  2. Discontinuous Mode Power Supply

    Science.gov (United States)

    Lagadinos, John; Poulos, Ethel

    2012-01-01

    A document discusses the changes made to a standard push-pull inverter circuit to avoid saturation effects in the main inverter power supply. Typically, in a standard push-pull arrangement, the unsymmetrical primary excitation causes variations in the volt second integral of each half of the excitation cycle that could lead to the establishment of DC flux density in the magnetic core, which could eventually cause saturation of the main inverter transformer. The relocation of the filter reactor normally placed across the output of the power supply solves this problem. The filter reactor was placed in series with the primary circuit of the main inverter transformer, and is presented as impedance against the sudden changes on the input current. The reactor averaged the input current in the primary circuit, avoiding saturation of the main inverter transformer. Since the implementation of the described change, the above problem has not reoccurred, and failures in the main power transistors have been avoided.

  3. Integrated Main Propulsion System Performance Reconstruction Process/Models

    Science.gov (United States)

    Lopez, Eduardo; Elliott, Katie; Snell, Steven; Evans, Michael

    2013-01-01

    The Integrated Main Propulsion System (MPS) Performance Reconstruction process provides the MPS post-flight data files needed for postflight reporting to the project integration management and key customers to verify flight performance. This process/model was used as the baseline for the currently ongoing Space Launch System (SLS) work. The process utilizes several methodologies, including multiple software programs, to model integrated propulsion system performance through space shuttle ascent. It is used to evaluate integrated propulsion systems, including propellant tanks, feed systems, rocket engine, and pressurization systems performance throughout ascent based on flight pressure and temperature data. The latest revision incorporates new methods based on main engine power balance model updates to model higher mixture ratio operation at lower engine power levels.

  4. Comparative Analysis of the Main Business Intelligence Solutions

    OpenAIRE

    Alexandra RUSANEANU

    2013-01-01

    Nowadays, Business Intelligence solutions are the main tools for analyzing and monitoring the company’s performance at any organizational level. This paper presents a comparative analysis of the most powerful Business Intelligence solutions using a set of technical features such as infrastructure of the platform, development facilities, complex analysis tools, interactive dashboards and scorecards, mobile integration and complex implementation of performance management methodologies.

  5. Understanding, modeling, and improving main-memory database performance

    OpenAIRE

    Manegold, S.

    2002-01-01

    textabstractDuring the last two decades, computer hardware has experienced remarkable developments. Especially CPU (clock-)speed has been following Moore's Law, i.e., doubling every 18 months; and there is no indication that this trend will change in the foreseeable future. Recent research has revealed that database performance, even with main-memory based systems, can hardly benefit from the ever increasing CPU power. The reason for this is that the performance of other hardware components h...

  6. Motor-generator set of the PS main supply

    CERN Multimedia

    Photographic Service; CERN PhotoLab

    1968-01-01

    Already in 1964, the PS improvement programme included a new main magnet supply with more power for the longer cycles needed for slow extraction at the full energy of 26 GeV. This motor-generator set was installed in 1967 and took up service at the beginning of 1968. Regularly serviced and fitted with modern electronic regulation, it pulses the PS to this day.

  7. Improvement on main control room for Japanese PWR plants

    International Nuclear Information System (INIS)

    Matsumiya, Masayuki

    1996-01-01

    The main control room which is the information center of nuclear power plant has been continuously improved utilizing the state of the art ergonomics, a high performance computer, computer graphic technologies, etc. For the latest Japanese Pressurized Water Reactor (PWR) plant, the CRT monitoring system is applied as the major information source for facilitating operators' plant monitoring tasks. For an operating plant, enhancement of monitoring and logging functions has been made adopting a high performance computer

  8. Measurement of the transfer function of the main SPS Quadrupoles

    CERN Document Server

    Dinius, A; Semanaz, P; CERN. Geneva. SPS and LEP Division

    1998-01-01

    During two short MD's we have measured the transfer function (amplitude and phase) of the main quadrupole string QD. By the word string we mean the global effect of power supplies, magnets and the eddy current effects of the vacuum chamber. This paper presents the measurement procedure and the results, which are needed for the design of a real-time feedback system for the betatron tunes ( Qloop).

  9. China and nuclear power

    International Nuclear Information System (INIS)

    Fouquoire-Brillet, E.

    1999-01-01

    This book presents the history of nuclear power development in China from the first research works started in the 1950's for the manufacturing of nuclear weapons to the recent development of nuclear power plants. This study tries to answer the main questions raised by the attitude of China with respect to the civil and military nuclear programs. (J.S.)

  10. Function analysis and function assignment of NPP advanced main control room

    International Nuclear Information System (INIS)

    Zheng Mingguang; Xu Jijun

    2001-01-01

    The author addresses the requirements of function analysis and function assignment, which should be carried out in the design of main control room in nuclear power plant according to the design research of advanced main control room, then states its contents, functions, importance and necessity as well as how to implement these requirements and how to do design verification and validation in the design of advanced main control room of nuclear power plant

  11. MECAR (Main Ring Excitation Controller and Regulator): A real time learning regulator for the Fermilab Main Ring or the Main Injector synchrotron

    International Nuclear Information System (INIS)

    Flora, R.; Martin, K.; Moibenko, A.; Pfeffer, H.; Wolff, D.; Prieto, P.; Hays, S.

    1995-04-01

    The real time computer for controlling and regulating the FNAL Main Ring power supplies has been upgraded with a new learning control system. The learning time of the system has been reduced by an order of magnitude, mostly through the implementation of a 95 tap FIR filter in the learning algorithm. The magnet system consists of three buses, which must track each other during a ramp from 100 to 1700 amps at a 2.4 second repetition rate. This paper will present the system configuration and the tools used during development and testing

  12. 46 CFR 58.25-10 - Main and auxiliary steering gear.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Main and auxiliary steering gear. 58.25-10 Section 58.25... AUXILIARY MACHINERY AND RELATED SYSTEMS Steering Gear § 58.25-10 Main and auxiliary steering gear. (a) Power-operated main and auxiliary steering gear must be separate systems that are independent throughout their...

  13. Economic Operation of Power Systems with Significant Wind Power Penetration

    DEFF Research Database (Denmark)

    Farashbashi-Astaneh, Seyed-Mostafa

    This dissertation addresses economic operation of power systems with high penetration of wind power. Several studies are presented to address the economic operation of power systems with high penetration of variable wind power. The main concern in such power systems is high variability...... and unpredictability. Unlike conventional power plants, the output power of a wind farm is not controllable. This brings additional complexity to operation and planning of wind dominant power systems. The key solution in face of wind power uncertainty is to enhance power system flexibility. The enhanced flexibility......, cooperative wind-storage operation is studied. Lithium-Ion battery units are chosen as storage units. A novel formulation is proposed to investigate optimal operation of a storage unit considering power system balancing conditions and wind power imbalances. An optimization framework is presented to increase...

  14. MATHEMATIC SIMULATION OF TRANSIENT PROCESS IN A. C – SYSTEM “ELECTRIC – TRACTION – NETWORK – LOCOMOTIVE” 2. SWITCH ON THE MAIN LOCOMOTIVE’S POWER CONVERTER IN “FREE PAY” MODE; DEFINITION AND ANALYSIS CURRENT SURGE OF MAGNETIZATION

    Directory of Open Access Journals (Sweden)

    T. M. Mischenko

    2010-12-01

    Full Text Available The article is a continuation of analysis of mathematical models for AC systems, in which the elements of electric-traction network and switch-on of power transformer in an idling mode are gradually connected. The numerical calculations and analysis of current of transformer magnetization are executed.

  15. Main approaches to the study of loss

    Directory of Open Access Journals (Sweden)

    Burina E. A.

    2016-07-01

    Full Text Available this article presents the main approaches to the concepts of grief and loss study. The article describes the contribution of E. Lindemann, Z. Freud, J. Bowlby, F.E. Vasiluk, and E. Kubler-Ross. The research also contains the main forms of grief and some stadial models within the scope of problematics.

  16. Nitrogen chronology of massive main sequence stars

    NARCIS (Netherlands)

    Köhler, K.; Borzyszkowski, M.; Brott, I.; Langer, N.; de Koter, A.

    2012-01-01

    Context. Rotational mixing in massive main sequence stars is predicted to monotonically increase their surface nitrogen abundance with time. Aims. We use this effect to design a method for constraining the age and the inclination angle of massive main sequence stars, given their observed luminosity,

  17. Engineering Design of KSTAR tokamak main structure

    International Nuclear Information System (INIS)

    Im, K.H.; Cho, S.; Her, N.I.

    2001-01-01

    The main components of the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak including vacuum vessel, plasma facing components, cryostat, thermal shield and magnet supporting structure are in the final stage of engineering design. Hundai Heavy Industries (HHI) has been involved in the engineering design of these components. The current configuration and the final engineering design results for the KSTAR main structure are presented. (author)

  18. Riigikogu maine ja armastus / Aune Past

    Index Scriptorium Estoniae

    Past, Aune, 1954-

    2007-01-01

    Autor arutleb Riigikogu maine üle, toetudes TÜ ajakirjanduse ja kommunikatsiooni osakonna 2007. aastal tehtud uuringu tulemustele. Riigikogu liikmete maine paraneks, kui neil endil oleks selge, mis eesmärgil Toompeale mindi ja sellest siis ka rahvale kõneldaks

  19. Politics and Politicians – Main Topic and Main Characters on Television News

    Directory of Open Access Journals (Sweden)

    Viktorija Car

    2010-01-01

    Full Text Available The paper examines the relationship between television as a medium, and politics and politicians as the content of television news in Croatia. The first part of the paper explains the models of ‘media logic’, ‘partisan logic’ and ‘party logic’. The second part of the paper presents the results of the research conducted on the representative sample of primetime news HTV Dnevnik for the period 1991-2009, and Nova TV Dnevnik and RTL Vijesti for the period 2005-2009. The goal of the research was to examine the presence of political topics on primetime news, as well to what extent politicians are presented as main characters. The results show a sustained decline of politics on the news and their simultaneous replacement by news on disasters and lifestyle. Further, citizens and their opinion become more important than opinions of politicians, experts and scientists. Comparing the news on public service television and on commercial televisions, the author elaborates on the internal processes and changes of the television medium and finally introduces the concept of ‘power logic’ to explain news selection and news editing on the Croatian TV channels.

  20. Hydroelectric Power Plants Dobsina

    International Nuclear Information System (INIS)

    Majercak, V.; Srenkelova, Z.; Kristak, J.G.

    1997-01-01

    In this brochure the Hydroelectric Power Plants Dobsina, (VED), subsidiary of the utility Slovenske Elektrarne, a.s. (Slovak Electric, plc. Bratislava) are presented. VED is mainly aimed at generating peak-load electrical energy and maintenance of operational equipment. Reaching its goals, company is first of all focused on reliability of production, economy and effectiveness, keeping principles of work safety and industry safety standards and also ecology. VED operates eight hydroelectric power plants, from which PVE Ruzin I and PVE Dobsina I are pump storage ones and they are controlled directly by the Slovak Energy Dispatch Centre located in Zilina thought the system LS 3200. Those power plants participate in secondary regulation of electrical network of Slovakia. They are used to compensate balance in reference to foreign electrical networks and they are put into operation independently from VED. Activity of the branch is focused mainly on support of fulfilment of such an important aim as electric network regulation. Beginnings of the subsidiary Hydroelectric Power Plants Dobsina are related to the year of 1948. After commissioning of the pump storage Hydroelectric Power Plants Dobsina in 1953, the plant started to carry out its mission. Since that time the subsidiary has been enlarged by other seven power plants, through which it is fulfilling its missions nowadays. The characteristics of these hydroelectric power plants (The pump-storage power plant Dobsina, Small hydroelectric power plant Dobsina II, Small hydroelectric power plant Rakovec, Small hydroelectric power plant Svedlar, Hydroelectric power plant Domasa, The pump-storage power plant Ruzin, and Small hydroelectric power plant Krompachy) are described in detail. Employees welfare and public relations are presented

  1. Hillshades for the main 8 Hawaiian Islands

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — These hillshade datasets were derived from USGS 7.5' DEM Quads for the main 8 Hawaiian Islands. Individual DEM quads were first converted to a common datum, and...

  2. Seasonal Composite Chlorophyll Concentrations - Gulf of Maine

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This personal geodatabase contains raster images of chlorophyll concentrations in the Gulf of Maine. These raster images are seasonal composites, and were calculated...

  3. Collins' bypass for the main ring

    International Nuclear Information System (INIS)

    Ohnuma, S.

    1982-01-01

    Design of the bypass for the main ring at Fermilab is discussed. Specific design features discussed include space, path length, geometric closure, matching of betatron functions, and external dispersion. Bypass parameters are given

  4. Monthly Composite Chlorophyll Concentrations - Gulf of Maine

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This personal geodatabase contains raster images of chlorophyll concentrations in the Gulf of Maine. These raster images are monthly composites, and were calculated...

  5. 2015 City of Portland, Maine, Lidar

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — 2015 City of Portland Maine Lidar Data Acquisition and Processing Woolpert Order No. 75564 Contractor: Woolpert, Inc. This task is for a high resolution data set of...

  6. 2016 USGS Lidar DEM: Maine QL2

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Product: These are Digital Elevation Model (DEM) data for Franklin, Oxford, Piscataquis, and Somerset Counties, Maine as part of the required deliverables for the...

  7. Molecular clusters of the main group elements

    CERN Document Server

    Driess, Matthias

    2008-01-01

    ""To summarize, Molecular Clusters of the Main Group Elements is certainly not a popular science book, nor is it a textbook; it is a very good, up-to-date collection of articles for the specialist. Als Fazit bleibt: Molecular Clusters of the Main Group Elements ist sicher kein populissenschaftliches Werk, auch kein Lehrbuch, aber eine gelungene, hoch aktuelle Zusammenstellung fen interessierten Fachmann."" -Michael Ruck, TU Dresden, Angewandte Chemie, 2004 - 116/36 + International Edition 2004 - 43/36

  8. Revisiting Reuse in Main Memory Database Systems

    OpenAIRE

    Dursun, Kayhan; Binnig, Carsten; Cetintemel, Ugur; Kraska, Tim

    2016-01-01

    Reusing intermediates in databases to speed-up analytical query processing has been studied in the past. Existing solutions typically require intermediate results of individual operators to be materialized into temporary tables to be considered for reuse in subsequent queries. However, these approaches are fundamentally ill-suited for use in modern main memory databases. The reason is that modern main memory DBMSs are typically limited by the bandwidth of the memory bus, thus query execution ...

  9. Analysis and evaluation of the main factors that influence the growing of the electrical power consumption in the national electrical sector, period 2000-2005; Analisis y evaluacion de los principales factores que influyen en el crecimiento del consumo de energia electrica en el sector electrico nacional, periodo 2000-2005

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar Luna, Luis Miguel

    2008-06-15

    With the purpose of avoiding the installation of new transmission lines, some researches have proposed the installation of SIFLETCA devices. Therefore in this thesis, different models in steady state of diverse SIFLETCA devices are described, such as: compensator variable series (VSC), static compensator of VArs (SCV), transformer phase shifter (TPS), transformer with changer under load (TWCL) and the universal controller of power flows (UCPF). In addition, it is developed in this thesis the equations used in the Jacobean of the method Newton-Raphson, to solve power flows including SIFLETCA devices. The different applications that are obtained when installing a device, such as prevention of flows in ring, electronic barrier, increment in the transmission capacity and specification of the power flow in transmission lines. On the other hand in the thesis, an analysis of sensitivities of a power system in steady state is developed. Also the control parameters are proposed in the thesis for which the sensitivities are calculated. Also, a performance index is used to measure the degree of congestion of an electrical system. In calculating the sensitivities the obtained results of the power flows are utilized. Four electrical networks are used to find where each SIFLETCA device must be located to reduce the congestion in the system. Also, the method developed in the thesis is compared with a method of sensitivities that uses DC flows, for validation and to show the advantages of using the Newton method in power flows. [Spanish] Con el fin de evitar instalar nuevas lineas de transmision, algunos investigadores han propuesto la instalacion de los dispositivos SIFLETCA. Por lo tanto en esta tesis, se describe diferentes modelos en estado estacionario de diversos dispositivos SIFLETCA, siendo: compensador serie variable (CSV), compensador estatico de VArs (CEV), transformador desfasador (TD), transformador con cambiador bajo carga (TTC) y el controlador universal de flujos

  10. 600W uninterruptible power supply

    Energy Technology Data Exchange (ETDEWEB)

    Frizell, C

    1988-01-01

    Although the mains power supply in western Europe is normally reliable, power failures, transients and noise can cause loss or corruption of data held on personal computers. The design of an uninterruptible power supply system (UPS) based on well proven technology, is described.

  11. Investigation and comparison of the main corrosion processes on different electric power substations of the Rio Grande de Sul state, Brazil; Investigacao e comparacao dos principais processos de corrosao em diferentes subestacoes de energia eletrica do estado do Rio Grande do Sul

    Energy Technology Data Exchange (ETDEWEB)

    Brusamarello, Valner; Bianchi, Andre L.; Rieder, Ester S.; Balbinot, Alexandre; Wentz, Marcio; Konig, Diogo; Radke, Carlos [Universidade Luterana do Brasil (Ulbra), Canoas, RS (Brazil)

    2006-07-01

    In this work experiments have been developed on four electric power substations, three located at the coastal of the state of Rio Grande do Sul and one at the capital od the state, Porto Alegre city. The study had the objective to determine the corrosion ratios of the different metallic materials exposed to aggressive agents of the environment where the substations are exposed, and to determine the corrosive attack mechanisms of those materials as well, viewing the optimization using of those materials for a more extended useful life.

  12. China's power policy

    International Nuclear Information System (INIS)

    Mayer, M.

    2006-01-01

    Whether the People's Republic of China may develop to an economical super-government in future depends on the amount of power and resources of this land. The security of power supply is in an extremely prominent position in the Agenda of the Chinese government. Under this aspect the author of the contribution under consideration reports on the power policy of China. The main aspects of this contribution are: (a) Trends of power consumption, productions and imports of power; (b) Power political targets, measures and instruments of China; (c) Characteristics, national and international impacts of the power policy of China. Due to the economical activities of the chinese oil industry worldwide as well as due to the increasing dependence from imports of petroleum and natural oil, China becomes a global player. Thus, one may expect an intensification of Beijing's economical activities with an increased military component. Nevertheless, the power policy of China is an important factor in the global competition according to fossil resources. In order to understand the future behaviour of China's power policy, one may have to take notice of the strategies relating the power policy and relating to foreign affairs. Furthermore, trends and problematic areas concerning the securitization of the power supply in the national area have to be observed

  13. Renewable energies in France: main 2003 results

    International Nuclear Information System (INIS)

    2004-05-01

    This document makes a synthesis of the power and thermal productions linked with renewable energy sources (of primary or secondary origin) for 2003. It details the uses (electrical or thermal) of the different renewable energy sources and their contribution to the different users' needs (residential, industry, agriculture..). A comparison with the previous years (2001 and 2002) is presented in tables. (J.S.)

  14. Karlsruhe nuclear research center. Main activities

    International Nuclear Information System (INIS)

    The article reports on problems of securing the fuel supply for nuclear power generation, on reprocessing and ultimate storage of radioactive material, on the safety of nuclear facilities, on new technologies and basic research, and on the infrastructure of the Karlsruhe nuclear research center, as well as finance and administration. (HK) [de

  15. Comparative economics of the main electricity sources

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1991-01-01

    Few participants in the Uranium Institute's Symposium would fail to agree that nuclear power has considerable environmental and ecological advantages over fossil fuel combustion. There would, however, be far less unanimity, even among a favourably inclined group, on the economic attractiveness of nuclear power and its competitive position vis-a-vis other electricity generation options. To the layman the conflicting claims are confusing, not least because nuclear power often appears to be the only product surrounded by such controversy. Some of the principal reasons are listed. Of these, deficiencies in understanding and divergent value standards are identified as particularly important. The latter issue has a major effect on comparative economics, when incorporated into the calculations of the cost of nuclear power when compared to its alternatives. In this paper the nature of the comparisons that can usefully be made is defined, then the results of recent international studies and their implications are outlined. Confusions arising from the privatisation of the electricity supply industry in the United Kingdom are examined and the implications of taking a wider view of economic comparisons are examined. (author)

  16. Main building fire drill safely concluded

    CERN Document Server

    CERN Bulletin

    2015-01-01

    Last week, a simulated fire in the stairwell of the Main Building put CERN’s emergency response procedures to the test.   Firefighters descend the stairwell in the Main Building as the simulated fire rises.   At 2 p.m. on 22 September, alarms sounded around CERN’s Main Building as an evacuation exercise got underway. A simulated fire in the  stairwell, complete with very realistic smoke, led to the evacuation of one of the busiest places at CERN. The Main Building complex includes the Carlson Wagonlit travel agency, the post office, UBS, Uniqa, the Users Office, the Staff Association and the Novae restaurant as well as the Main Auditorium, the Council Chamber and the Charpak meeting room. It was impressive to see how quickly the smoke propagated in the staircase as well as into the corridors, and equally impressive to see how smoothly, quickly and efficiently the evacuation proceeded. The...

  17. 15 theses on power

    Directory of Open Access Journals (Sweden)

    Susen Simon

    2014-01-01

    Full Text Available This article seeks to contribute to a critical understanding of the multifaceted nature of power, emphasizing its capacity to shape the development of society by permeating constitutive aspects of human reality. To this end, the article proposes an outline of a multidimensional approach to power. It does so by identifying and examining several - arguably universal - features and functions of power. On the basis of 15 theses, it is argued that, within the social world, the power of power derives from the fact that it is (1 ubiquitous, (2 productive, (3 relational, (4 intangible, (5 habitual, (6 discursive, (7 corporeal, (8 polycentric, (9 performative, (10 normative, (11 spatial, (12 temporal, (13 disciplinary, (14 circular, and (15 transcendental. By way of conclusion, the article provides a comprehensive summary of the main insights gained and challenges arising from such a multidimensional approach to power.

  18. Study on the main control room design for Hamaoka Unit No.5

    International Nuclear Information System (INIS)

    Tsuruta, Tadakazu; Sakamoto, Minoru; Maruyama, Tohru; Saito, Tadashi

    2000-01-01

    The main control room of nuclear power station is important to operate the power station and to promote public acceptance of nuclear power station. To enhance them, there is an idea of high ceiling control room with a gallery room located in backside middle upper floor. The control room is expected to enhance habitability and to offer visitors the fine view of the control room. In this study, psychological and physiological influence of such a high ceiling control room design on operators was investigated first. And then some human engineering requirements for desirable main control room were identified. A control room (ceiling height: about 5 meters) adequate to the requirements was designed, and finally the validity of the design was verified by means of full mockup model room tests. The results of this study are applied to the main control room design of Hamaoka Nuclear Power Station Unit No.5 (Chubu Electric Power Co., Inc.) (author)

  19. Main Coast Winds - Final Scientific Report

    Energy Technology Data Exchange (ETDEWEB)

    Jason Huckaby; Harley Lee

    2006-03-15

    The Maine Coast Wind Project was developed to investigate the cost-effectiveness of small, distributed wind systems on coastal sites in Maine. The restructuring of Maine's electric grid to support net metering allowed for the installation of small wind installations across the state (up to 100kW). The study performed adds insight to the difficulties of developing cost-effective distributed systems in coastal environments. The technical hurdles encountered with the chosen wind turbine, combined with the lower than expected wind speeds, did not provide a cost-effective return to make a distributed wind program economically feasible. While the turbine was accepted within the community, the low availability has been a negative.

  20. Space Shuttle main engine product improvement

    Science.gov (United States)

    Lucci, A. D.; Klatt, F. P.

    1985-01-01

    The current design of the Space Shuttle Main Engine has passed 11 certification cycles, amassed approximately a quarter million seconds of engine test time in 1200 tests and successfully launched the Space Shuttle 17 times of 51 engine launches through May 1985. Building on this extensive background, two development programs are underway at Rocketdyne to improve the flow of hot gas through the powerhead and evaluate the changes to increase the performance margins in the engine. These two programs, called Phase II+ and Technology Test Bed Precursor program are described. Phase II+ develops a two-tube hot-gas manifold that improves the component environment. The Precursor program will evaluate a larger throat main combustion chamber, conduct combustion stability testing of a baffleless main injector, fabricate an experimental weld-free heat exchanger tube, fabricate and test a high pressure oxidizer turbopump with an improved inlet, and develop and test methods for reducing temperature transients at start and shutdown.

  1. Pragmatic power

    CERN Document Server

    Eccles, William

    2008-01-01

    Pragmatic Power is focused on just three aspects of the AC electrical power system that supplies and moves the vast majority of electrical energy nearly everywhere in the world: three-phase power systems, transformers, and induction motors. The reader needs to have had an introduction to electrical circuits and AC power, although the text begins with a review of the basics of AC power. Balanced three-phase systems are studied by developing their single-phase equivalents. The study includes a look at how the cost of ""power"" is affected by reactive power and power factor. Transformers are cons

  2. Intelligent Power Management of hybrid Wind/ Fuel Cell/ Energy Storage Power Generation System

    OpenAIRE

    A. Hajizadeh; F. Hassanzadeh

    2013-01-01

    This paper presents an intelligent power management strategy for hybrid wind/ fuel cell/ energy storage power generation system. The dynamic models of wind turbine, fuel cell and energy storage have been used for simulation of hybrid power system. In order to design power flow control strategy, a fuzzy logic control has been implemented to manage the power between power sources. The optimal operation of the hybrid power system is a main goal of designing power management strategy. The hybrid ...

  3. High-ratio voltage conversion in CMOS for efficient mains-connected standby

    CERN Document Server

    Meyvaert, Hans

    2016-01-01

    This book describes synergetic innovation opportunities offered by combining the field of power conversion with the field of integrated circuit (IC) design. The authors demonstrate how integrating circuits enables increased operation frequency, which can be exploited in power converters to reduce drastically the size of the discrete passive components. The authors introduce multiple power converter circuits, which are very compact as result of their high level of integration. First, the limits of high-power-density low-voltage monolithic switched-capacitor DC-DC conversion are investigated to enable on-chip power granularization. AC-DC conversion from the mains to a low voltage DC is discussed, enabling an efficient and compact, lower-power auxiliary power supply to take over the power delivery during the standby mode of mains-connected appliances, allowing the main power converter of these devices to be shut down fully. Discusses high-power-density monolithic switched-capacitor DC-DC conversion in bulk CMOS,...

  4. Transition crossing in the main injector

    International Nuclear Information System (INIS)

    Wei, J.

    1990-01-01

    This report summarizes the study of various longitudinal problems pertaining to the transition-energy crossing in the proposed Fermi Lab Main Injector. The theory indicates that the beam loss and bunch-area growth are mainly caused by the chromatic non-linear effect, which is enhanced by the space-charge force near transition. Computer simulation using the program TIBETAN shows that a ''γ T jump'' of about 1.5 unit within 1 ms is adequate to achieve a ''clean'' crossing in the currently proposed h=588 scenario. 19 refs., 4 figs

  5. The Fermilab Main Injector Technical Design Handbook

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1994-08-01

    This report contains a description of the design, cost estimate, and construction schedule of the Fermilab Main Injector (FMI) Project. The technical, cost, and schedule baselines for the FMI Project have already been established and may be found in the Fermilab Main Injector Title I Design Report, issued in August 1992. This report updates and expands upon the design and schedule for construction of all subsystem components and associated civil construction described in the Title I Design Report. The facilities described have been designed in conformance with DOE 6430.1A, "United States Department of Energy General Design Criteria."

  6. Current Russian patriotism: matter, features, main directions

    Directory of Open Access Journals (Sweden)

    Lutovinov Vladimir Ilich

    2013-11-01

    Full Text Available The article considers understanding and the main point of patriotism as one of high cultural values. The main approaches that reveal different sides of this phenomenon, its role and importance in a history of Russia in the 21st century are inferred from the analysis of viewpoints of Russian thinkers and contemporary researchers. The patriotism formation problems in Russian society and their condition are defined, the need of patriotic level rise as one of the conditions for great Russia rebirth is substantiated.

  7. Bunch coalescing in the Fermilab Main Ring

    International Nuclear Information System (INIS)

    Wildman, D.; Martin, P.; Meisner, K.; Miller, H.W.

    1987-01-01

    A new RF system has been installed in the Fermilab Main Ring to coalesce up to 13 individual bunches of protons or antiprotons into a single high-intensity bunch. The coalescing process consists of adiabatically reducing the h=1113 Main Ring RF voltage from 1 MV to less than 1 kV, capturing the debunched beam in a linearized h=53 and h=106 bucket, rotating for a quarter of a synchrotron oscillation period, and then recapturing the beam in a single h=1113 bucket. The new system is described and the results of recent coalescing experiments are compared with computer-generated particle tracking simulations

  8. Comparative studies between nuclear power plants and hydroelectric power plants

    International Nuclear Information System (INIS)

    Menegassi, J.

    1984-01-01

    This paper shows the quantitative evolution of the power plants in the main countries of the world. The Brazilian situation is analysed, with emphasys in the technical and economical aspects related to power production by hidroelectric or nuclear power plants. The conclusion is that the electricity produced by hidro power plants becomes not economics when is intended to be produced at large distances from the demand centers. (Author) [pt

  9. Status of Wind Power Technologies

    DEFF Research Database (Denmark)

    Zhao, Haoran; Wu, Qiuwei

    2018-01-01

    With the development of wind turbine technology, wind power will become more controllable and grid‐friendly. It is desirable to make wind farms operate as conventional power plants. Wind turbine generators (WTGs) were mainly used in rural and remote areas for wind power generation. WTG‐based wind...... energy conversion systems (WECS) can be divided into the four main types (type 1‐4). Due to the inherent variability and uncertainty of the wind, the integration of wind power into the grid has brought challenges in several different areas, including power quality, system reliability, stability......, and planning. The impact of each is largely dependent on the level of wind power penetration in the grid. In many countries, relatively high levels of wind power penetration have been achieved. This chapter shows the estimated wind power penetration in leading wind markets....

  10. Main principles of development stationary training facilities

    International Nuclear Information System (INIS)

    Tsiptsyura, R.D.

    1986-01-01

    The designation of stationary training facilities is shown and the main requirements for them are formulated. When considering the above-mentioned requirements, special attention was paid to obligatory correspondence between training experience and practical skill of an operator. It is shown, that the switchboard block is the major unit of the training facility, which should develop skills and habits of an operator

  11. Live insertion method used for main renewal

    International Nuclear Information System (INIS)

    Solkowitz, M.

    1992-01-01

    Baltimore Gas and Electric's pilot project using the live insertion method to replace a cast iron main provided excellent results. Its use on Eastern Avenue, a major state highway, was cost effective, provided gas service to customers during the work, required relatively short construction time and resulted in only minor traffic disruptions. Gas service transfers to the new main were done at customer convenience and resulted in outages of only a few hours per customer. This paper reports that the project involved inserting a 6-in. plastic line inside an existing 10-in. cast iron main. Miller Pipeline Corp., Indianapolis, supplier of the Insertec left-angle R right-angle live insertion method was contracted for the job. Miller technicians assisted BG and E forces by providing a load analysis of the main, a pushing machine and related supplies, foaming equipment and pipe cutting tools. Company forces were responsible for all preparatory work, including opening all excavations, installing bypasses, and fusing and testing the plastic pipe. Service transfers and renewals were also completed by company employees

  12. Maine Project against Bullying. Final Report.

    Science.gov (United States)

    Saufler, Chuck; Gagne, Cyndi

    Noting that bullying among primary school-age children has become recognized as an antecedent to more violent behavior in later grades, the 3-year Maine Project Against Bullying examined currently available research on bullying and evaluated books, curricula, media materials, and programs to identify resources and strategies which can be applied…

  13. Modern Portfolio Theory: Some Main Results

    OpenAIRE

    Müller, Heinz H.

    2017-01-01

    This article summarizes some main results in modern portfolio theory. First, the Markowitz approach is presented. Then the capital asset pricing model is derived and its empirical testability is discussed. Afterwards Neumann-Morgenstern utility theory is applied to the portfolio problem. Finally, it is shown how optimal risk allocation in an economy may lead to portfolio insurance

  14. Main successes, achievements. Paths of development

    Directory of Open Access Journals (Sweden)

    A. A. Kubanova

    2015-01-01

    Full Text Available The article provides the overview of incidence of sexually transmitted infections and skin disorders over time in Russian Federation in 2004-2014 with its main positive tendencies; results of reorganisation of bed capacity of dermatovenerologic medical organizations; dermatovenerologic bed rates.

  15. Space transportation main engine reliability and safety

    Science.gov (United States)

    Monk, Jan C.

    1991-01-01

    Viewgraphs are used to illustrate the reliability engineering and aerospace safety of the Space Transportation Main Engine (STME). A technology developed is called Total Quality Management (TQM). The goal is to develop a robust design. Reducing process variability produces a product with improved reliability and safety. Some engine system design characteristics are identified which improves reliability.

  16. Water Hammer in Pumped Sewer Mains

    DEFF Research Database (Denmark)

    Larsen, Torben

    This publication is intended for engineers seeking an introduction to the problem of water hammer in pumped pressure mains. This is a subject of increasing interest because of the development of larger and more integrated sewer systems. Consideration of water hammer is essential for structural...

  17. VINKA, ten years on. Main scientific results

    International Nuclear Information System (INIS)

    1979-01-01

    The VINKA facility in the TRITON swimming-pool reactor at Fontenay-aux-Roses allows the irradiation of solids at low temperatures in order to study crystalline defects. After ten years of operation the main scientific results obtained in the fields of creep and growth (chapter I), point defects (chapter II), amorphisation (chapter III) and dechanneling of particles (chapter IV) are summarised [fr

  18. Results on Fermilab main injector dipole measurements

    International Nuclear Information System (INIS)

    Brown, B.C.; Baiod, R.; DiMarco, J.; Glass, H.D.; Harding, D.J.; Martin, P.S.; Mishra, S.; Mokhtarani, A.; Orris, D.F.; russell, O.A.; Tompkins, J.C.; Walbridge, D.G.C.

    1995-06-01

    Measurements of the Productions run of Fermilab Main Injector Dipole magnets is underway. Redundant strength measurements provide a set of data which one can fit to mechanical and magnetic properties of the assembly. Plots of the field contribution from the steel supplement the usual plots of transfer function (B/I) vs. I in providing insight into the measured results

  19. On power and empowerment.

    Science.gov (United States)

    Pratto, Felicia

    2016-03-01

    This study presents a conceptual analysis of social power. The most common theories of power are social-relational, an approach instantiated in a range of contemporary experiments that give participants the chance to control other people's outcomes. The relational approach is also reflected in various analyses of international relations. In comparing and contrasting relational theories of power, I identify logical inconsistencies and shortcomings in their ability to address empowerment and reductions in inequality. In turn, I propose a new ecological conceptualization of empowerment as the state of being able to achieve one's goals and of power as stemming from a combination of the capacity of the party and the affordances of the environment. I explain how this new conceptualization can describe the main kinds of power social relations, avoid logical contradictions, and moreover, distinguish power from agency and from control. This new conceptualization of power as the possibility of meeting goals, coupled with recognizing survival as the fundamental goal of all living things, implies an absolute and not relative or relational standard for power, namely well-being. It also allows us to conceive of power in ways that help address the many social concerns that have motivated research on power. © 2015 The British Psychological Society.

  20. Thermal power measurement apparatus

    International Nuclear Information System (INIS)

    1981-01-01

    Thermal power measurements are important in nuclear power plants, fossil-fuel plants and other closed loop systems such as heat exchangers and chemical reactors. The main object of this invention is to determine the enthalpy of a fluid using only acoustically determined sound speed and correlating the speed with enthalpy. An enthalpy change is measured between two points in the fluid flow: the apparatus is described in detail. (U.K.)

  1. Power corrupts

    International Nuclear Information System (INIS)

    Bacon, H.; Valentine, J.

    1981-01-01

    The subject is covered in chapters, entitled: radiation (hazards associated with nuclear power production); wastes (radioactive wastes); accidents (actual and postulated, resulting in the release of radiation); the FBR and the plutonium cycle; costs (economics of nuclear power); spent fuel transport; civil liberties; doing without nuclear power (UK power demand; low energy strategy; energy policy; government policies; alternative energy sources). (U.K.)

  2. The five roads. Main report from the project Energy Crossroads

    International Nuclear Information System (INIS)

    2009-09-01

    . Energy Crossroads is aimed at decision-makers who are in a position to influence energy policy. The main idea has been to use analysis and discussion to identify the measures that provide the most climate benefits for the money. We have identified five areas - or directions - which we believe are the most important. Direction 1. Prioritise energy efficiency as the overall energy policy instrument. Sweden can save 15 TWh by improving energy efficiency with the control mechanisms currently in place. With 'market pricing' for emissions the most cost-effective measures will be implemented first. Instead of detailed regulation and costly initiatives, we will have a long-term reduction in total energy consumption. Energy efficiency improvement is also saleable internationally, profitable from a public finances perspective and a concrete concept for energy consumers. There is still great potential for the use of residual heat by our industries, for both internal and external use. Direction 2. Invest in measures that are the most beneficial for the climate. Increasing the percentage of energy we get from renewable sources does not automatically lower greenhouse gas emissions. We should increase the percentage of renewable energy, but a forced expansion would be unreasonably expensive. If implemented with today's support systems, the renewable energy objective and today's plans for expanding wind power up to 30 TWh would be costly for Sweden's electricity consumers unless alternative financing is found. Expanding wind power requires investment in the power grid, expanding reserve power (hydropower) and raising subsidies. Expanding wind power too much could lead to sur surplus electricity and wind power exporting - paid for by Sweden's electricity consumers. There are more cost-effective ways of reducing greenhouse gases. The renewable energy goal should steer us towards reducing the use of fossil fuels - not a one-sided investment in a single climate-friendly alternative

  3. Condition monitoring of main coolant pumps, Dhruva

    International Nuclear Information System (INIS)

    Prasad, V.; Satheesh, C.; Acharya, V.N.; Tikku, A.C.; Mishra, S.K.

    2002-01-01

    Full text: Dhruva is a 100 MW research reactor with natural uranium fuel, heavy water as moderator and primary coolant. Three Centrifugal pumps circulate the primary coolant across the core and the heat exchangers. Each pump is coupled to a flywheel (FW) assembly in order to meet operational safety requirements. All the 3 main coolant pump (MCP) sets are required to operate during operation of the reactor. The pump-sets are in operation since the year 1984 and have logged more than 1,00,000 hrs. Frequent breakdowns of its FW bearings were experienced during initial years of operation. Condition monitoring of these pumps, largely on vibration based parameters, was initiated on regular basis. Break-downs of main coolant pumps reduced considerably due to the fair accurate predictions of incipient break-downs and timely maintenance efforts. An effort is made in this paper to share the experience

  4. Alarm system for ABWR main control panels

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Yuji; Saito, Koji [Toshiba Corp., Yokohoma (Japan)

    1997-09-01

    TOSHIBA has developed integrated digital control and instrumentation system for ABWR, which is the third-generation man machine interface system for main control room that we call A-PODIA (Advanced PODIA). A-Podia has been introduced the first actual ABWR plant in Japan. in A-PODIA, TOSHIBA has realized improvement of alarm system that all operator crews in the control room can recognize plant anomalies easily. The alarm system can recognize essential alarms for plant safety easily and understand annunciators with each integrated annunciators and their prioritized color easily by classifying alarms into plant-level essential annunciators, system-level integrated annunciators and equipment level individual annunciators with hierarchical structure. This paper describes conventional alarm system and the design philosophy, alarm system design and operation of ``Alarm System for ABWR Main Control Panels``. (author). 5 refs, 8 figs, 1 tab.

  5. Chromaticity compensation scheme for the Main Injector

    International Nuclear Information System (INIS)

    Bogacz, S.A.

    1993-05-01

    The current Main Injector lattice is studied in the context of full chromaticity compensation in the presence of the eddy current, saturation and the end-pack sextupole fields generated by the dipole magnets. Two families of correcting sextupole magnets are placed to compensate these fields and to adjust the chromaticity (in both planes) to some desired value. Variation of the dipole induced sextupole fields with the B-field (changing along a ramp) are modeled according to recent experimental measurements of the Main Injector dipole magnet Analysis of the required sextupole strengths is carried out along two realistic momentum ramps. The results of our calculation give quantitative insight into the requisite performance of the sextupole magnets

  6. Installation Strategy for the LHC Main Dipoles

    CERN Multimedia

    Fartoukh, Stephane David

    2004-01-01

    All positions in the LHC machine are not equivalent in terms of beam requirements on the geometry and the field quality of the main dipoles. In the presence of slightly or strongly out-of tolerance magnets, a well-defined installation strategy will therefore contribute to preserve or even optimize the performance of the machine. Based on the present status of the production, we have anticipated a list of potential issues (geometry, transfer function, field direction and random b3) which, combined by order of priority, have been taken into account to define a simple but efficient installation algorithm for the LHC main dipoles. Its output is a prescription for installing the available dipoles in sequence while reducing to an absolute minimum the number of holes required by geometry or FQ issues.

  7. The LHC Main Quadrupoles during Series Fabrication

    CERN Document Server

    Tortschanoff, Theodor; Durante, M; Hagen, P; Klein, U; Krischel, D; Payn, A; Rossi, L; Schellong, B; Schmidt, P; Simon, F; Schirm, K-M; Todesco, E

    2006-01-01

    By the end of August 2005 about 320 of the 400 main LHC quadrupole magnets have been fabricated and about 220 of them assembled into their cold masses, together with corrector magnets. About 130 of them have been cold tested in their cryostats and most of the quadrupoles exceeded their nominal excitation, i.e. 12,000 A, after no more than two training quenches. During this series fabrication, the quality of the magnets and cold masses was thoroughly monitored by means of warm magnetic field measurements, of strict geometrical checking, and of various electrical verifications. A number of modifications were introduced in order to improve the magnet fabrication, mainly correction of the coil geometry for achieving the specified field quality and measures for avoiding coil insulation problems. Further changes concern the electrical connectivity and insulation of instrumentation, and of the corrector magnets inside the cold masses. The contact resistances for the bus-bar connections to the quench protection diode...

  8. The double main sequence of Omega Centauri

    Science.gov (United States)

    Bedin, L. R.; Piotto, G.; Anderson, J.; King, I. R.; Cassisi, S.; Momany, Y.

    Recent, high precision photometry of Omega Centauri, the biggest Galactic globular cluster, has been obtained with Hubble Space Telescope (HST). The color magnitude diagram reveals an unexpected bifurcation of colors in the main sequence (MS). The newly found double MS, the multiple turnoffs and subgiant branches, and other sequences discovered in the past along the red giant branch of this cluster add up to a fascinating but frustrating puzzle. Among the possible explanations for the blue main sequence an anomalous overabundance of helium is suggested. The hypothesis will be tested with a set of FLAMES@VLT data we have recently obtained (ESO DDT program), and with forthcoming ACS@HST images. Based on observations with the NASA/ESA Hubble Space Telescope, obtained at the Space Telescope Science Institute, which is operated by AURA, Inc., under NASA contract NAS 5-26555.

  9. Alarm system for ABWR main control panels

    International Nuclear Information System (INIS)

    Kobayashi, Yuji; Saito, Koji

    1997-01-01

    TOSHIBA has developed integrated digital control and instrumentation system for ABWR, which is the third-generation man machine interface system for main control room that we call A-PODIA (Advanced PODIA). A-Podia has been introduced the first actual ABWR plant in Japan. in A-PODIA, TOSHIBA has realized improvement of alarm system that all operator crews in the control room can recognize plant anomalies easily. The alarm system can recognize essential alarms for plant safety easily and understand annunciators with each integrated annunciators and their prioritized color easily by classifying alarms into plant-level essential annunciators, system-level integrated annunciators and equipment level individual annunciators with hierarchical structure. This paper describes conventional alarm system and the design philosophy, alarm system design and operation of ''Alarm System for ABWR Main Control Panels''. (author). 5 refs, 8 figs, 1 tab

  10. INNOVATION DIFFUSION THEORY MAIN DEVELOPMENT STAGES

    Directory of Open Access Journals (Sweden)

    S. V. Lisafiev

    2011-01-01

    Full Text Available Abstract: Main innovation diffusion development theory stages are: Rogers model of moving new products to the market including characteristics of its segments; mathematic substantiation of this model by Bass; Moor model taking into account gaps between adjacent market segments; Goldenberg model making it possible to predict sales drops at new product life cycle initial stages. It is reasonable to use this theory while moving innovative products to the market.

  11. Space shuttle main engine vibration data base

    Science.gov (United States)

    Lewallen, Pat

    1986-01-01

    The Space Shuttle Main Engine Vibration Data Base is described. Included is a detailed description of the data base components, the data acquisition process, the more sophisticated software routines, and the future data acquisition methods. Several figures and plots are provided to illustrate the various output formats accessible to the user. The numerous vibration data recall and analysis capabilities available through automated data base techniques are revealed.

  12. The Main Properties of q-Functions

    OpenAIRE

    Nina O. Virchenko; Olena V. Ovcharenko

    2017-01-01

    Background.  The new generalization of the function of complex variable (q-function) is considered, its main properties are investigated. Such distributions have a special place among the special functions due to their widespread use in many areas of applied mathematics. Objective. The aim of the paper is to study the new generalization of the function of complex variable for application in applied sciences. Methods. To obtain scientific results the general methods of the mathematical a...

  13. Radiation shielding of the main injector

    International Nuclear Information System (INIS)

    Bhat, C.M.; Martin, P.S.

    1995-05-01

    The radiation shielding in the Fermilab Main Injector (FMI) complex has been carried out by adopting a number of prescribed stringent guidelines established by a previous safety analysis. Determination of the required amount of radiation shielding at various locations of the FMI has been done using Monte Carlo computations. A three dimensional ray tracing code as well as a code based upon empirical observations have been employed in certain cases

  14. Post-main-sequence planetary system evolution

    Science.gov (United States)

    Veras, Dimitri

    2016-01-01

    The fates of planetary systems provide unassailable insights into their formation and represent rich cross-disciplinary dynamical laboratories. Mounting observations of post-main-sequence planetary systems necessitate a complementary level of theoretical scrutiny. Here, I review the diverse dynamical processes which affect planets, asteroids, comets and pebbles as their parent stars evolve into giant branch, white dwarf and neutron stars. This reference provides a foundation for the interpretation and modelling of currently known systems and upcoming discoveries. PMID:26998326

  15. The BTeV main spectrometer

    International Nuclear Information System (INIS)

    Sheldon, P.D.

    2001-01-01

    BTeV is a second generation B-factory experiment that will use a double-arm, forward spectrometer in the C0 experimental hall at the Fermilab Tevatron. I will describe the motivation and design of the 'main spectrometer', consisting of a ring-imaging Cherenkov system for charged particle identification, an electromagnetic calorimeter of lead-tungstate crystals, a proportional tube muon system with magnetized filtering steel, and a straw-tube and silicon strip charged particle tracking system

  16. Main-sequence photometry in NGC 2808

    International Nuclear Information System (INIS)

    Buonanno, R.; Corsi, C.E.; Fusi Pecci, F.; Harris, W.E.

    1984-01-01

    We have obtained a color-magnitude diagram for the southern globular cluster NGC 2808, to V/sub lim/approx. =21 (about 2 mag below the main-sequence turnoff). The internal photographic errors are sigma/sub V/approx. =0.02, sigma/sub B/-Vapprox. =0.03, small enough to permit a precise definition of the turnoff region and an estimate of the ''cosmic scatter'' along the main sequence. Fitting of the CMD to VandenBerg's [Astrophys. J. Suppl. 51, 29 (1983)] isochrones shows that an excellent match to the observations is achieved for model parameters of Yapprox. =0.2, Zapprox. =0.003 ([Fe/H]approx. =-0.8), and an age of (16 +- 2) billion years. All these characteristics are within the expected range from other observational constraints; no new clues from the main-sequence data alone have arisen to help explain the presence of the anomalous blue horizontal-branch stars

  17. 46 CFR 28.820 - Fire pumps, fire mains, fire hydrants, and fire hoses.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Fire pumps, fire mains, fire hydrants, and fire hoses... REQUIREMENTS FOR COMMERCIAL FISHING INDUSTRY VESSELS Aleutian Trade Act Vessels § 28.820 Fire pumps, fire mains, fire hydrants, and fire hoses. (a) Each vessel must be equipped with a self-priming, power driven fire...

  18. DC Pollution of AC Mains due to modern compact fluorescent light lamps and LED lamps

    NARCIS (Netherlands)

    Keyer, Cornelis H.A.; Timens, R.B.; Buesink, Frederik Johannes Karel; Leferink, Frank Bernardus Johannes

    2013-01-01

    Modern so-called energy efficient equipment often draw current only during a very short period of the period of a power supply mains. This is causing unwanted non-sinusoidal and harmonic currents. In some cases even a single diode is used for rectification causing direct current (DC) in the mains

  19. Power quality assessment

    International Nuclear Information System (INIS)

    Fathi, H.M.E.

    2012-01-01

    The electrical power systems are exposed to different types of power quality disturbances problems. Assessment of power quality is necessary for maintaining accurate operation of sensitive equipment's especially for nuclear installations, it also ensures that unnecessary energy losses in a power system are kept at a minimum which lead to more profits. With advanced in technology growing of industrial / commercial facilities in many region. Power quality problems have been a major concern among engineers; particularly in an industrial environment, where there are many large-scale type of equipment. Thus, it would be useful to investigate and mitigate the power quality problems. Assessment of Power quality requires the identification of any anomalous behavior on a power system, which adversely affects the normal operation of electrical or electronic equipment. The choice of monitoring equipment in a survey is also important to ascertain a solution to these power quality problems. A power quality assessment involves gathering data resources; analyzing the data (with reference to power quality standards); then, if problems exist, recommendation of mitigation techniques must be considered. The main objective of the present work is to investigate and mitigate of power quality problems in nuclear installations. Normally electrical power is supplied to the installations via two sources to keep good reliability. Each source is designed to carry the full load. The Assessment of power quality was performed at the nuclear installations for both sources at different operation conditions. The thesis begins with a discussion of power quality definitions and the results of previous studies in power quality monitoring. The assessment determines that one source of electricity was deemed to have relatively good power quality; there were several disturbances, which exceeded the thresholds. Among of them are fifth harmonic, voltage swell, overvoltage and flicker. While the second

  20. Cuba’s Critical Juncture: Main Challenges

    Directory of Open Access Journals (Sweden)

    Vegard Bye

    2017-11-01

    Full Text Available Cuba is rapidly approaching a critical juncture, where a complete and generational change of leadership is unavoidable (between 2018 and 2021. The country and its Revolution is up against some unavoidable and complicated choices in the coming four years. With the rapidly approaching end of the Castro era, without any clear new leadership structure in sight, and with an apparently unsolvable economic crisis and rapidly shrinking confidence in the political power bloc particularly among the younger generations, a deep legitimacy crisis is looming. What are the principal challenges ahead, and how can and will they be solved?

  1. Kozloduy Nuclear Power Plant (Unit 1 and 2). Proposed modifications to increase the seismic capability of equipment and main structures; Central Nuclear de Kozloduy (Unidades 1 y 2). Modificaciones propuestas a los equipos y estructuras principales para incrementar su capacidad sismica

    Energy Technology Data Exchange (ETDEWEB)

    Ordonez Villalobos, A [Empresarios Agrupados, A.I.E., Madrid (Spain); Monette, P R [Westinghouse Energy Systems International (WESI), Bussels (Belgium)

    1993-12-15

    Within the framework of the European Community's PHARE Programme of improvement to facilities, their operating systems, equipment and buildings of the Kozloduy NPP in Bulgaria, plant safety during seismic events is considered to be an issue of overriding importance, especially in view of the earthquakes the region suffered during the last decade. Westinghouse Energy Systems International (WESI) and Empresarios Agrupados (EA) have initiated an intensive programme for physical upgrading of equipment with a view to augmenting its seismic capability and, at the same time, to studying design modifications in the diesel-generator buildings, pump house and main building structures (turbines, electrical building). The implementation of these modifications requires an in situ inspection of the real conditions of the various elements, analyses, conceptual design and detail engineering, all of which has to be done in short periods of time using resources available at the plant. This activity is performed by the companies mentioned above, with the collaboration of two engineering companies, Energoproekt of Bulgaria and INITEC of Spain. This paper describes the activities developed and the treatment given to the various aspects of improvement of the seismic capability of equipment and structures. (author)

  2. Mobile nuclear power systems

    International Nuclear Information System (INIS)

    Andersson, B.

    1988-11-01

    This report is meant to present a general survey of the mobile nuclear power systems and not a detailed review of their technical accomplishments. It is based in published material mainly up to 1987. Mobile nuclear power systems are of two fundamentally different kinds: nuclear reactors and isotopic generators. In the reactors the energy comes from nuclear fission and in the isotopic generators from the radioactive decay of suitable isotopes. The reactors are primarily used as power sourves on board nuclear submarines and other warships but have also been used in the space and in remote places. Their thermal power has ranged from 30 kWth (in a satellite) to 175 MWth (on board an aircraft carrier). Isotopic generators are suitable only for small power demands and have been used on board satellites and spaceprobes, automatic weatherstations, lighthouses and marine installations for navigation and observation. (author)

  3. Dynamic influences of wind power on the power system

    Energy Technology Data Exchange (ETDEWEB)

    Rosas, Pedro

    2003-03-01

    The thesis first presents the basics influences of wind power on the power system stability and quality by pointing out the main power quality issues of wind power in a small-scale case and following, the expected large-scale problems are introduced. Secondly, a dynamic wind turbine model that supports power quality assessment of wind turbines is presented. Thirdly, an aggregate wind farm model that support power quality and stability analysis from large wind farms is presented. The aggregate wind farm model includes the smoothing of the relative power fluctuation from a wind farm compared to a single wind turbine. Finally, applications of the aggregate wind farm model to the power systems are presented. The power quality and stability characteristics influenced by large-scale wind power are illustrated with three cases. In this thesis, special emphasis has been given to appropriate models to represent the wind acting on wind farms. The wind speed model to a single wind turbine includes turbulence and tower shadow effects from the wind and the rotational sampling turbulence due to the rotation of the blades. In a park scale, the wind speed model to the wind farm includes the spatial coherence between different wind turbines. Here the wind speed model is applied to a constant rotational speed wind turbine/farm, but the model is suitable to variable speed wind turbine/farm as well. The cases presented here illustrate the influences of the wind power on the power system quality and stability. The flicker and frequency deviations are the main power quality parameters presented. The power system stability concentrates on the voltage stability and on the power system oscillations. From the cases studied, voltage and the frequency variations were smaller than expected from the large-scale wind power integration due to the low spatial correlation of the wind speed. The voltage quality analysed in a Brazilian power system and in the Nordel power system from connecting large

  4. Power conditioning devices in nuclear power plants

    International Nuclear Information System (INIS)

    Shida, Toichi.

    1979-01-01

    Purpose: To automatically prevent the liquid level from lowering in a reactor even if a feedwater adjusting valve is locked in a bwr type nuclear power plant. Constitution: Where a feedwater adjusting valve should be locked, and if the mismatching degree between the main steam flow rate and the feedwater flow rate exceeds a predetermined value and the mismatched state continues for a certain period, the value set to a main control for setting the recycling flow rate is changed corresponding to the mismatching degree to compensate the same thereby preventing the liquid level from lowering in the reactor. (Ikeda, J.)

  5. Study on the task categorization of main control room in NPP

    International Nuclear Information System (INIS)

    Fang Zhou; Ma Zhicai; Ma Xusheng; Zheng Mingguang

    2005-01-01

    The paper states the importance and trendy requirements of Main Control Room (MCR) in nuclear power plant and introduces how to implement the human factor engineering principle in the design of advanced main control room. It mainly focuses on the purpose and functions, strategy and methodology, scope and contents of the MCR task categorization. The preliminary MCR task categorization is performed according to these principles. (authors)

  6. Rates of the main thermonuclear reactions

    International Nuclear Information System (INIS)

    Abramovich, S.N.; Guzhovskii, B.Ya.; Dunaeva, S.A.; Fomushkin, E.F.

    1992-01-01

    The data on the cross sections of main thermonuclear reactions have been estimated with an account of the latest experimental results in a form of S-factor spline presentation. Based on this estimation, the reates of these reactions in 0.0001-1 MeV temperature range in the supposition of Maxwell distribution of relative velocities have been computed. The Maxwell-Boltzmann averaged -factors were calculated according to the table values of the reaction rates. Then the -factors were approximated with the 3 order spline-function. The necessity of the account of electron shielding and intramolecular movement at low temperatures is discussed (orig.)

  7. Musculoskeletal disorders in main battle tank personnel

    DEFF Research Database (Denmark)

    Nissen, Lars Ravnborg; Guldager, Bernadette; Gyntelberg, Finn

    2009-01-01

    PURPOSE: To compare the prevalence of musculoskeletal disorders of personnel in the main battle tank (MBT) units in the Danish army with those of personnel in other types of army units, and to investigate associations between job function in the tank, military rank, and musculoskeletal problems......, and ankle. RESULTS AND CONCLUSIONS: There were only 4 women in the MBT group; as a consequence, female personnel were excluded from the study. The participation rate was 58.0% (n = 184) in the MBT group and 56.3% (n = 333) in the reference group. The pattern of musculoskeletal disorders among personnel...

  8. Main problems of modern radiation hygiene

    International Nuclear Information System (INIS)

    Il'in, L.A.; Buldakov, L.A.; Knizhnikov, V.A.

    1982-01-01

    The results of investigations carried out in 1980-81 in the field of radiation hygiene as well as plans for 1981-85 are considered. Three main groups of problems which the radiation hygiene is facing at the present time are discussed. The determination of levels and study of regularities of ionizing radiation dose formation in the population and personnel working with ionizing radiation sources in one of the promissing directions of the investigations. Delayed irradiation aftereffects andcontaminant action ofirradiation and chemical substances are no less important. The third important problem lies in the development of protective measures and arrangements on improving state sanitary inspection in the field of radiation hygiene

  9. Some peat deposits in Penobscot County, Maine

    Science.gov (United States)

    Cameron, Cornelia Clermont; Anderson, Walter A.

    1979-01-01

    Twenty of the peat deposits in Penobscot County, Maine contain an estimated 29,282,000 short tons air-dried peat. The peat is chiefly sphagnum moss and reed-sedge of high quality according to ASTM standards for agricultural and horticultural use. Analyses show that this same volume has high fuel value, low sulfur and high hydrogen contents compared with lignite and sub-bituminous coal, which may indicate that it also has potential for fuel use. On the basis of the metallic trace element content, one area within the region containing the 20 deposits has been delineated for further bedrock studies.

  10. Main-chain supramolecular block copolymers.

    Science.gov (United States)

    Yang, Si Kyung; Ambade, Ashootosh V; Weck, Marcus

    2011-01-01

    Block copolymers are key building blocks for a variety of applications ranging from electronic devices to drug delivery. The material properties of block copolymers can be tuned and potentially improved by introducing noncovalent interactions in place of covalent linkages between polymeric blocks resulting in the formation of supramolecular block copolymers. Such materials combine the microphase separation behavior inherent to block copolymers with the responsiveness of supramolecular materials thereby affording dynamic and reversible materials. This tutorial review covers recent advances in main-chain supramolecular block copolymers and describes the design principles, synthetic approaches, advantages, and potential applications.

  11. Additively Manufactured Main Fuel Valve Housing

    Science.gov (United States)

    Eddleman, David; Richard, Jim

    2015-01-01

    Selective Laser Melting (SLM) was utilized to fabricate a liquid hydrogen valve housing typical of those found in rocket engines and main propulsion systems. The SLM process allowed for a valve geometry that would be difficult, if not impossible to fabricate by traditional means. Several valve bodies were built by different SLM suppliers and assembled with valve internals. The assemblies were then tested with liquid nitrogen and operated as desired. One unit was also burst tested and sectioned for materials analysis. The design, test results, and planned testing are presented herein.

  12. Water Hammer in Pumped Sewer Mains

    DEFF Research Database (Denmark)

    Larsen, Torben

    of transients in pumped pipeline systems. This present publication can be understood as the second and revised edition of the pamphlet ”Transients in pumped sewer mains” (2006) which was published as a technical report by The EVA committee under The Danish Water Pollution Committee (The Danish Society......This publication is intended for students and engineers seeking an introduction to the problem of water transients in pumped sewer and water mains. This is a subject of increasing interest because of the development of larger and more integrated systems. Consideration of transients is essential...

  13. Space Shuttle Main Engine Public Test Firing

    Science.gov (United States)

    2000-01-01

    A new NASA Space Shuttle Main Engine (SSME) roars to the approval of more than 2,000 people who came to John C. Stennis Space Center in Hancock County, Miss., on July 25 for a flight-certification test of the SSME Block II configuration. The engine, a new and significantly upgraded shuttle engine, was delivered to NASA's Kennedy Space Center in Florida for use on future shuttle missions. Spectators were able to experience the 'shake, rattle and roar' of the engine, which ran for 520 seconds - the length of time it takes a shuttle to reach orbit.

  14. Main challenges in demulsifier research and application

    Science.gov (United States)

    Zhang, Fusheng; Liu, Guoliang; Ma, Junhan; Ouyang, Jian; Yi, Xiaoling; Su, Huimin

    2017-01-01

    Main challenges in demulsifier research, such as demulsification of ASP flooding produced liquid, demulsification of heavy oil produced liquid, low temperature demulsification and fast demulsification, are summarized. Some importance technology routes to solve the challenges are proposed according to demulsification mechanisms and emulsion characteristics. The proposed routes include increasing aromaticity, molecular weight and branch degree of demulsifiers, and introducing double-function groups to demulsifiers for W/O and O/W emulsions, or groups with alkyl matching with alkyl carbon number of the crude oil into demulsifier molecule. The demulsification mechanisms of the above-mentioned research routes are described in detail.

  15. Main feedwater valve diagnostics at Waterford 3 nuclear generating station

    International Nuclear Information System (INIS)

    Fitzgerald, W.V.

    1991-01-01

    Pneumatically-operated control valves are coming under increasing scrutiny in nuclear power plants because of their relatively high incident rate. The theory behind a device that could make performance evaluation of these valves simpler and more effective was first described at the original EPRI Power Plant Valve Symposium. The development of this Diagnostic System was completed in 1989, and it was recently used to troubleshoot two main feedwater valves at Louisiana Power and Light's Waterford 3 Power Station. During a cold snap last December, these valves failed to respond to the input signal and, as a result, the plant came off line. An incident report had to be filed, and the plant chose to contact the original equipment manufacturer (OEM) for assistance. This paper describes the original incident involving these valves and then gives a brief description of the diagnostic system and how it works. The balance of the paper then reviews how the OEM and plant personnel utilized the system to evaluate each component of the control valve assembly (I/P transducer, positioner, volume boosters, actuator, and valve body assembly). By simply stroking the valve and monitoring pneumatic signals and valve position, the problem was traced to a malfunctioning positioner and a volume booster that was leaking. The problems were corrected and new performance signatures run for the valves using the system to document their improved operation. This case study demonstrates how new Diagnostic Technology along with OEM involvement can effectively address problems with pneumatically-operated control valves so that root-cause solutions can be implemented

  16. Forensic entomology and main challenges in Brazil.

    Science.gov (United States)

    Gomes, Leonardo; Von Zuben, Cláudio J

    2006-01-01

    Apart from an early case report from China (13th century), the first observations on insects and other arthropods as forensic indicators were documented in Germany and France during mass exhumations in the 1880s by Reinhard, who is considered a co-founder of the discipline. After the French publication of Mégnin's popular book on the applied aspects of forensic entomology, the concept quickly spread to Canada and United States. At that time, researchers recognized that the lack of systematic observations of insects of forensic importance jeopardized their use as indicators of postmortem interval. General advances in insect taxonomy and ecology helped to fill this gap over the following decades. After World Wars, few forensic entomology cases were reported in the scientific literature. From 1960s to the 1980s, Leclercq and Nuorteva were primarily responsible for maintaining the method in Central Europe, reporting isolated cases. Since then, basic research in the USA, Russia and Canada opened the way to the routine use of Entomology in forensic investigations. Identifications of insects associated with human cadavers are relatively few in the literature of the Neotropical region and have received little attention in Brazil. This article brings an overview of historic developments in this field, the recent studies and the main problems and challenges in South America and mainly in Brazil.

  17. Main Issues in Big Data Security

    Directory of Open Access Journals (Sweden)

    Julio Moreno

    2016-09-01

    Full Text Available Data is currently one of the most important assets for companies in every field. The continuous growth in the importance and volume of data has created a new problem: it cannot be handled by traditional analysis techniques. This problem was, therefore, solved through the creation of a new paradigm: Big Data. However, Big Data originated new issues related not only to the volume or the variety of the data, but also to data security and privacy. In order to obtain a full perspective of the problem, we decided to carry out an investigation with the objective of highlighting the main issues regarding Big Data security, and also the solutions proposed by the scientific community to solve them. In this paper, we explain the results obtained after applying a systematic mapping study to security in the Big Data ecosystem. It is almost impossible to carry out detailed research into the entire topic of security, and the outcome of this research is, therefore, a big picture of the main problems related to security in a Big Data system, along with the principal solutions to them proposed by the research community.

  18. Power generation statistics

    International Nuclear Information System (INIS)

    Kangas, H.

    2001-01-01

    The frost in February increased the power demand in Finland significantly. The total power consumption in Finland during January-February 2001 was about 4% higher than a year before. In January 2001 the average temperature in Finland was only about - 4 deg C, which is nearly 2 degrees higher than in 2000 and about 6 degrees higher than long term average. Power demand in January was slightly less than 7.9 TWh, being about 0.5% less than in 2000. The power consumption in Finland during the past 12 months exceeded 79.3 TWh, which is less than 2% higher than during the previous 12 months. In February 2001 the average temperature was - 10 deg C, which was about 5 degrees lower than in February 2000. Because of this the power consumption in February 2001 increased by 5%. Power consumption in February was 7.5 TWh. The maximum hourly output of power plants in Finland was 13310 MW. Power consumption of Finnish households in February 2001 was about 10% higher than in February 2000, and in industry the increase was nearly zero. The utilization rate in forest industry in February 2001 decreased from the value of February 2000 by 5%, being only about 89%. The power consumption of the past 12 months (Feb. 2000 - Feb. 2001) was 79.6 TWh. Generation of hydroelectric power in Finland during January - February 2001 was 10% higher than a year before. The generation of hydroelectric power in Jan. - Feb. 2001 was nearly 2.7 TWh, corresponding to 17% of the power demand in Finland. The output of hydroelectric power in Finland during the past 12 months was 14.7 TWh. The increase from the previous 12 months was 17% corresponding to over 18% of the power demand in Finland. Wind power generation in Jan. - Feb. 2001 was exceeded slightly 10 GWh, while in 2000 the corresponding output was 20 GWh. The degree of utilization of Finnish nuclear power plants in Jan. - Feb. 2001 was high. The output of these plants was 3.8 TWh, being about 1% less than in Jan. - Feb. 2000. The main cause for the

  19. Fusion power

    International Nuclear Information System (INIS)

    Hancox, R.

    1981-01-01

    The principles of fusion power, and its advantages and disadvantages, are outlined. Present research programmes and future plans directed towards the development of a fusion power reactor, are summarized. (U.K.)

  20. Power Electronics

    DEFF Research Database (Denmark)

    Iov, Florin; Ciobotaru, Mihai; Blaabjerg, Frede

    2008-01-01

    is to change the electrical power production sources from the conventional, fossil (and short term) based energy sources to renewable energy resources. The other is to use high efficient power electronics in power generation, power transmission/distribution and end-user application. This paper discuss the most...... emerging renewable energy sources, wind energy, which by means of power electronics are changing from being a minor energy source to be acting as an important power source in the energy system. Power electronics is the enabling technology and the presentation will cover the development in wind turbine...... technology from kW to MW, discuss which power electronic solutions are most feasible and used today....

  1. Normative Power

    DEFF Research Database (Denmark)

    's normative power than any other academic journal, including a special issue on "What Kind of Power?" in 2006. As the leading journal in the debate, this special issue brings together seven normative power articles published in JEPP since the 2006 special issue, together with Ian Manners' ‘Normative power......The social sciences have many different understandings of ‘normative power', but in European Union (EU) studies normative power has three particular meanings. The first meaning of normative power is its emphasis on normative theory, that is, how we judge and justify truth claims in social science...... effects of EU relations with the world in areas ranging from inter-regional relations, through traditional diplomacy, to environmental politics. Research areas of particular interest include the study of the interplay between physical, material and normative forms of power, as well as the constitutive...

  2. Nuclear power publications

    International Nuclear Information System (INIS)

    1982-01-01

    This booklet lists 69 publications on nuclear energy available free from some of the main organisations concerned with its development and operation in the UK. Headings are: general information; the need for nuclear energy; the nuclear industry; nuclear power stations; fuel cycle; safety; waste management. (U.K.)

  3. Power control device

    International Nuclear Information System (INIS)

    Fukawa, Naohiro.

    1982-01-01

    Purpose: To alleviate the load of an operator by automatically operating the main controller, the speed controller, etc. of a recirculation control system and safely operating them without erroneous operation for long period of time, thereby improving the efficiency of a plant. Constitution: An electric type hydraulic control device controls loads of a turbine and a generator and outputs a control signal also to the main controller of a recirculation flow rate control system. At this time, the main controller is set at an automatic position, and the speed controller receives a recirculation pump speed signal from the main controller at the automatic position. The speed controller outputs a pump speed control signal to the recirculation pump system, and a reactor generates a power corresponding thereto. When the power control is automatically performed by the recirculation flow rate control, an operator sets a rate of change of the recirculation pump speed and the rate of change of the mean power range monitor at a change rate setting unit. Therefore, the control of the recirculation flow rate under the power control can be substantially entirely automated. (Yoshigara, H.)

  4. Offshore Wind Power Data

    DEFF Research Database (Denmark)

    Cutululis, Nicolaos Antonio; Litong-Palima, Marisciel; Zeni, Lorenzo

    2012-01-01

    Wind power development scenarios are critical when trying to assess the impact of the demonstration at national and European level. The work described in this report had several objectives. The main objective was to prepare and deliver the proper input necessary for assessing the impact of Demo 4...

  5. Power marketing

    International Nuclear Information System (INIS)

    Sioshansi, F.P.; Altman, A.M.

    1998-01-01

    One of the most significant developments in the US electric power industry in recent years has been the phenomenal growth of power marketing. What was barely a blimp on the radar screen in 1992 has turned out to be a jumbo jet. This article explains what is power marketing who are power marketers, what role play these players and what will be their longer-term impact on the traditional industry [it

  6. Power Electronics

    Indian Academy of Sciences (India)

    They cover a wide spectrum of areas from power supplies to power system ... Ramanarayanan describe the modelling and design of a family of soft transition ... of power when the drive is operating in the braking mode and fast dynamic response. ... time models are extremely important, as they can be included in real time ...

  7. Main messages for the new nuclear unit in Finland

    International Nuclear Information System (INIS)

    Nikula, Anneli

    2001-01-01

    Teollisuuden Voima Oy (TVO) submitted last year, on 15th November, to the Council of State an application for a decision in principle concerning the construction of additional nuclear capacity. In this presentation, the main messages to decision makers for the new unit are discussed. Also the studies, which the messages are based on, are described. According to the Finnish Nuclear Energy Act, a company considering a nuclear plant project must apply for a decision in principle from the Government beforehand. The Government then decides whether the project is in accordance with the overall good of the society. If the decision is positive, it needs ratification by the Parliament. Before the Government decision, various interested parties are heard, including the municipality of location and the Radiation and Nuclear Safety Authority. The phase of statements is underway and they all will be ready by the end of March 2001. The entire application process takes approximately 1-2 years. The main messages arguing for more nuclear power in Finland were as follows. The new nuclear power plant unit replaces old fossil power plants and satisfies the need for additional demand of electricity; makes possible to meet the requirements of the Kyoto agreement; reduces the dependence on the imported energy and assures a stable and predictable electricity price. Messaging concerning a new nuclear power plant unit is made in co-operation with several organisations. The most important of them, in addition to the company shareholders, are the companies which have shown interested in the new project as well as the Finnish Energy Industries Federation (Finergy) and the Confederation of Finnish Industry and Employers. A transparency folder 'Nuclear electricity 2000' was put together of the messages in collaboration with the organisations. The folder was distributed to about 400 opinion leaders in the energy field. To ensure the consistency of the messages, several interest group meetings

  8. A random walk down Main Street

    Directory of Open Access Journals (Sweden)

    David Matthew Levinson

    2016-08-01

    Full Text Available US suburbs have often been characterized by their relatively low walk accessibility compared to more urban environments, and US urban environments have been char- acterized by low walk accessibility compared to cities in other countries. Lower overall density in the suburbs implies that activities, if spread out, would have a greater distance between them. But why should activities be spread out instead of developed contiguously? This brief research note builds a positive model for the emergence of contiguous development along “Main Street” to illustrate the trade-offs that result in the built environment we observe. It then suggests some policy interventions to place a “thumb on the scale” to choose which parcels will develop in which sequence to achieve socially preferred outcomes.

  9. Mortise terrorism on the main pipelines

    Science.gov (United States)

    Komarov, V. A.; Nigrey, N. N.; Bronnikov, D. A.; Nigrey, A. A.

    2018-01-01

    The research aim of the work is to analyze the effectiveness of the methods of physical protection of main pipelines proposed in the article from the "mortise terrorism" A mathematical model has been developed that made it possible to predict the dynamics of "mortise terrorism" in the short term. An analysis of the effectiveness of physical protection methods proposed in the article to prevent unauthorized impacts on the objects under investigation is given. A variant of a video analytics system has been developed that allows detecting violators with recognition of the types of work they perform at a distance of 150 meters in conditions of complex natural backgrounds and precipitation. Probability of detection is 0.959.

  10. Siberian snakes for the Fermilab Main Injector

    International Nuclear Information System (INIS)

    Anferov, V.A.; Baiod, R.; Courant, E.D.

    1993-01-01

    Appropriate Siberian snakes were designed to maintain the proton beam polarization during acceleration in the Fermilab Main Injector from 8 to 150 GeV. Various snake designs were investigated to find one fitting into the 14 m straight section spaces with the required spin rotation axis and the minimum orbit excursion. The authors studied both cold and warm discrete magnet snakes as well as warm snakes with helical magnets. For the warm discrete magnet snake, obtaining small orbit excursions required a nearly longitudinal snake axis, while axes near ±45 degrees are needed when using two snakes in a ring. The authors found acceptable snakes either by using superconducting magnets or by using warm magnets with a helical dipole field

  11. BANKING ETHICS: MAIN CONCEPTIONS AND PROBLEMS

    Directory of Open Access Journals (Sweden)

    VALENTINA FETINIUC

    2014-10-01

    Full Text Available Banking ethics is a specialized set of ethical standards and rules that should be followed in the activities of financial institutions and employees of the banking sector. But despite the simplicity of the definition, in the modern world, this concept becomes complex and ambiguous. The importance of studying this subject is defined by the fact that the ethical behavior of the bank and bank employees promotes banking. At present there are several conceptions of banking ethics: general ethics, regulated ethics and ethical bank. The most common practice is to regulate internal and external relations of banks and bank workers with ethical codes. At the same time, studies show the existence of problems in the banking standards of ethics, which negatively affects the financial institution. This article is intended to reflect main tendencies and problems of banking ethics at international level and experience of Republic of Moldova in this field.

  12. Seismic risks at Elsie Lake Main Dam

    International Nuclear Information System (INIS)

    McCammon, N.R.; Momenzadeh, M.; Hawson, H.H.; Nielsen, N.M.

    1991-01-01

    The Elsie Lake dams are located on Vancouver Island in an area of high seismic risk. A safety review in 1986 indicated potential deficiencies in the earthfill main dam with respect to modern earthquake design standards. A detailed field investigation program comprising drilling and penetration tests was carried out and the results used in an assessment of seismic stability. A 0.8 m thick less dense layer in the granular shell of the dam, possibly caused by wet construction conditions, would likely liquefy in a major earthquake but sufficient residual strength would likely remain to prevent catastrophic failure. The dam shell might undergo some distortion, and an assessment was initiated to determine the requirements for reservoir drawdown following an extreme earthquake to ensure the timely lowering of the reservoir for inspection and repair. It was suggested that an adequate evacuation capability would be 25% and 50% drawdown in not more than 30 and 50 days, respectively. 9 refs., 11 figs., 1 tab

  13. Natural syntax : English interrogative main clauses

    Directory of Open Access Journals (Sweden)

    Janez Oresnik

    2007-12-01

    Full Text Available Natural Syntax is a developing deductive theory, a branch of Naturalness Theory. The naturalnessjudgements are couched in naturalness scales, whichfollow from the basic parameters (or «axioms» listed at the beginning of the paper. The predictions of the theory are calculated in deductions, whose chief components are apair of naturalness scales and the rules governing the alignment of corresponding naturalness values. Parallel and chiastic alignments are distinguished, in complementary distribution. Chiastic alignment is mandatory in deductions limited to unnatural environments. The paper deals with English interrogative main clauses. Within these, only the interrogatives containing wh-words exclusively insitu constitute an extremely unnatural environment and require chiastic alignment. Otherwiseparallel alignment is used. Earlier publications on Natural Syntax: Kavcic 2005a,b, Oresnik 1999, 2000a,b, 200la-f   2002, 2003a-c, 2002/03, 2004. This list cites only works written in English.

  14. VAT EVASION INLEBANON: CASES AND MAIN CAUSES

    Directory of Open Access Journals (Sweden)

    Rana Ismail

    2012-07-01

    Full Text Available The Value Added Tax (VAT is a very important source oftreasuryrevenuesinLebanon. It was initially introduced inLebanon in order to reduce the budgetdeficit and help contain the debt. However, VAT evasion growth inLebanon isleading to significant VAT revenue losses because of its size and frequency.In this paper, we will highlight the contribution of VAT to the treasury revenue. Inaddition, our research has led to figure out the most significant VAT evasion casesand the way tax payers evade paying their required VAT or try to have an illegalrefund. From these tax evasion cases, we will pinpoint the main causes of suchevasions and propose solutions to limit as much as possible VAT evasion inLebanon.

  15. Main clinical epidemiological features of lung cancer

    International Nuclear Information System (INIS)

    Costa Montane, Daniel Marino; Prado Lage, Yulien; Lozano Salazar; Jorge Luis

    2011-01-01

    A descriptive and cross-sectional study of 95 patients with lung cancer, discharged from Neumology Service at 'Dr Juan Bruno Zayas Alfonso' General Hospital in Santiago de Cuba, was carried out from January, 2008 to December, 2008 in order to identify the main clinical epidemiological features of the aforementioned disease. A malignancy predominance among men aged between 56 and 65 years old, belonging to urban areas and being heavy smoker (out of 30 cigarettes per day over 30 years ), was found. Those affected without a confirmed histological type and IV clinical stage epidermoid carcinoma were predominant. Most of them had the opportunity to be treated. Increasing and intensifying health promotion and disease prevention campaigns were recommended so as to achieve the population to avoid or quit the smoking habit. (author)

  16. Main heat transfer components for SNR-300

    International Nuclear Information System (INIS)

    De Haas Van Dorsser, A.H.

    1976-01-01

    Early in the joint German-Belgium-Dutch fast breeder programme it was decided that all main components should be tested, if possible at full scale, before fabrication of the actual SNR-300 components. Descriptions are given of the results of testing, and subsequent modifications, of the pumps, intermediate heat exchangers, and steam generators. A full scale model of the primary pump, free surface vertical shaft centrifugal type, was constructed and tested in the 5000 cubic metres per hour pump test facility erected at Bensberg. A 70 MW model of an intermediate heat exchanger, straight tube type with floating head, was tested in the 50 MW steam generator test station at Hengelo. Also tested in the Hengelo facility was an almost full scale straight tube 50 MW steam generator and subsequently a 50 MW helical tube evaporator. The latter tests were of more than 3000 h operation and resulted in minor changes in design and manufacturing operation. (U.K.)

  17. Natural vibration experimental analysis of Novovoronezhskaya NPP main building

    International Nuclear Information System (INIS)

    Zoubkov, D.; Isaikin, A.; Shablinsky, G.; Lopanchuk, A.; Nefedov, S.

    2005-01-01

    1. Natural vibration frequencies are main characteristics of buildings and structures which allow to give integral estimation of their in-service state. Even relatively small changes of these frequencies as compared to the initially registered values point to serious defects of building structures. In this paper we analyzed natural vibration frequencies and natural modes of the main building (MB) of Novovoronezhskaya NPP operating nuclear unit with WWER-440 type reactor. The MB consists of a reactor compartment (RC), a machine room (MR) and an electric device (ED) unit positioned in between. 2. Natural vibration frequencies and natural modes of the MB were determined experimentally by analyzing its microvibrations caused by operation of basic equipment (turbines, pumps, etc.). Microvibrations of the main building were measured at 12 points. At each point measurements were carried out along two or three mutually perpendicular vibration directions. Spectral analysis of vibration records has been conducted. Identification of natural vibration frequencies was carried out on the basis of the spectral peaks and plotted vibration modes (taking into account operating frequencies of the basic equipment of the power generating unit). On the basis of the measurement results three transverse modes and corresponding natural vibration frequencies of the MB, one longitudinal mode and corresponding natural vibration frequency of the MB and two natural frequencies of vertical vibrations of RC and MR floor trusses (1st and 2nd symmetric forms) were determined. Dynamic characteristics of the main building of NV NPP resulting from full scale researches are supposed to be used as one of building structure stability criteria. (authors)

  18. The nuclear power generation

    International Nuclear Information System (INIS)

    Serres, R.

    1999-01-01

    The French nuclear generating industry is highly competitive. The installations have an average age of fifteen years and are half way through their expected life. Nuclear power accounts for 70% of the profits of the French generating company, EDF. Nuclear generation has a minimal effect on the atmosphere and France has a level of CO 2 emissions, thought to be the main cause of the greenhouse effect, half that of Europe as a whole. The air in France is purer than in neighbouring countries, mainly because 75% of all electrical power is generated in nuclear plants and 15% in hydroelectric stations. The operations and maintenance of French nuclear power plants in the service and distribution companies out of a total of 100 000 employees in all, 90 % of whom are based in mainland France. (authors)

  19. Wind Power Meteorology

    DEFF Research Database (Denmark)

    Lundtang Petersen, Erik; Mortensen, Niels Gylling; Landberg, Lars

    Wind power meteorology has evolved as an applied science, firmly founded on boundary-layer meteorology, but with strong links to climatology and geography. It concerns itself with three main areas: siting of wind turbines, regional wind resource assessment, and short-term prediction of the wind...... resource. The history, status and perspectives of wind power meteorology are presented, with emphasis on physical considerations and on its practical application. Following a global view of the wind resource, the elements of boundary layer meteorology which are most important for wind energy are reviewed......: wind profiles and shear, turbulence and gust, and extreme winds. The data used in wind power meteorology stem mainly from three sources: onsite wind measurements, the synoptic networks, and the re-analysis projects. Wind climate analysis, wind resource estimation and siting further require a detailed...

  20. Power converters for ITER

    CERN Document Server

    Benfatto, I

    2006-01-01

    The International Thermonuclear Experimental Reactor (ITER) is a thermonuclear fusion experiment designed to provide long deuterium– tritium burning plasma operation. After a short description of ITER objectives, the main design parameters and the construction schedule, the paper describes the electrical characteristics of the French 400 kV grid at Cadarache: the European site proposed for ITER. Moreover, the paper describes the main requirements and features of the power converters designed for the ITER coil and additional heating power supplies, characterized by a total installed power of about 1.8 GVA, modular design with basic units up to 90 MVA continuous duty, dc currents up to 68 kA, and voltages from 1 kV to 1 MV dc.