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Sample records for power bounded operators

  1. A van der Corput-type lemma for power bounded operators

    Czech Academy of Sciences Publication Activity Database

    ter Elst, A.F.M.; Müller, Vladimír

    2017-01-01

    Roč. 285, č. 1 (2017), s. 143-158 ISSN 0025-5874 R&D Projects: GA ČR(CZ) GA14-07880S EU Projects: European Commission(XE) 318910 - AOS Institutional support: RVO:67985840 Keywords : bounded semigroup of operators * mean ergodic theorem * polynomial Cesàro averages * power bounded operator Subject RIV: BA - General Mathematics OBOR OECD: Pure mathematics Impact factor: 0.738, year: 2016 http://link.springer.com/article/10.1007%2Fs00209-016-1701-2

  2. Robust nonlinear model predictive control for nuclear power plants in load following operations with bounded xenon oscillations

    International Nuclear Information System (INIS)

    Eliasi, H.; Menhaj, M.B.; Davilu, H.

    2011-01-01

    Research highlights: → In this work, a robust nonlinear model predictive control algorithm is developed. → This algorithm is applied to control the power level for load following. → The state constraints are imposed on the predicted trajectory during optimization. → The xenon oscillations are the main constraint for the load following problem. → In this algorithm, xenon oscillations are bounded within acceptable limits. - Abstract: One of the important operations in nuclear power plants is load-following in which imbalance of axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation considered to be a constraint for the load-following operation. In this paper, a robust nonlinear model predictive control for the load-following operation problem is proposed that ensures xenon oscillations are kept bounded within acceptable limits. The proposed controller uses constant axial offset (AO) strategy to maintain xenon oscillations to be bounded. The constant AO is a robust state constraint for load-following problem. The controller imposes restricted state constraints on the predicted trajectory during optimization which guarantees robust satisfaction of state constraints without restoring to a min-max optimization problem. Simulation results show that the proposed controller for the load-following operation is so effective so that the xenon oscillations kept bounded in the given region.

  3. Spectral computations for bounded operators

    CERN Document Server

    Ahues, Mario; Limaye, Balmohan

    2001-01-01

    Exact eigenvalues, eigenvectors, and principal vectors of operators with infinite dimensional ranges can rarely be found. Therefore, one must approximate such operators by finite rank operators, then solve the original eigenvalue problem approximately. Serving as both an outstanding text for graduate students and as a source of current results for research scientists, Spectral Computations for Bounded Operators addresses the issue of solving eigenvalue problems for operators on infinite dimensional spaces. From a review of classical spectral theory through concrete approximation techniques to finite dimensional situations that can be implemented on a computer, this volume illustrates the marriage of pure and applied mathematics. It contains a variety of recent developments, including a new type of approximation that encompasses a variety of approximation methods but is simple to verify in practice. It also suggests a new stopping criterion for the QR Method and outlines advances in both the iterative refineme...

  4. Cohering power of quantum operations

    Energy Technology Data Exchange (ETDEWEB)

    Bu, Kaifeng, E-mail: bkf@zju.edu.cn [School of Mathematical Sciences, Zhejiang University, Hangzhou 310027 (China); Kumar, Asutosh, E-mail: asukumar@hri.res.in [Harish-Chandra Research Institute, Chhatnag Road, Jhunsi, Allahabad 211019 (India); Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094 (India); Zhang, Lin, E-mail: linyz@zju.edu.cn [Institute of Mathematics, Hangzhou Dianzi University, Hangzhou 310018 (China); Wu, Junde, E-mail: wjd@zju.edu.cn [School of Mathematical Sciences, Zhejiang University, Hangzhou 310027 (China)

    2017-05-18

    Highlights: • Quantum coherence. • Cohering power: production of quantum coherence by quantum operations. • Study of cohering power and generalized cohering power, and their comparison for differentmeasures of quantum coherence. • Operational interpretation of cohering power. • Bound on cohering power of a generic quantum operation. - Abstract: Quantum coherence and entanglement, which play a crucial role in quantum information processing tasks, are usually fragile under decoherence. Therefore, the production of quantum coherence by quantum operations is important to preserve quantum correlations including entanglement. In this paper, we study cohering power–the ability of quantum operations to produce coherence. First, we provide an operational interpretation of cohering power. Then, we decompose a generic quantum operation into three basic operations, namely, unitary, appending and dismissal operations, and show that the cohering power of any quantum operation is upper bounded by the corresponding unitary operation. Furthermore, we compare cohering power and generalized cohering power of quantum operations for different measures of coherence.

  5. Architecture-independent power bound for vibration energy harvesters

    International Nuclear Information System (INIS)

    Halvorsen, E; Le, C P; Mitcheson, P D; Yeatman, E M

    2013-01-01

    The maximum output power of energy harvesters driven by harmonic vibrations is well known for a range of specific harvester architectures. An architecture-independent bound based on the mechanical input-power also exists and gives a strict limit on achievable power with one mechanical degree of freedom, but is a least upper bound only for lossless devices. We report a new theoretical bound on the output power of vibration energy harvesters that includes parasitic, linear mechanical damping while still being architecture independent. This bound greatly improves the previous bound at moderate force amplitudes and is compared to the performance of established harvester architectures which are shown to agree with it in limiting cases. The bound is a hard limit on achievable power with one mechanical degree of freedom and can not be circumvented by transducer or power-electronic-interface design

  6. Bounds on resolvents of dilated Schroedinger operators with non trapping potentials

    International Nuclear Information System (INIS)

    Duclos, P.; Klein, M.

    1985-06-01

    We provide bounds on resolvents of dilated Schroedinger operators via an exterior scaling. It is done under a non trapping condition on the potential which has a clear interpretation in classical mechanics. These bounds are a powerful tool to prove absence of resonances due to the tail of the potential in the shape resonance problem

  7. Operator continued fraction and bound states

    International Nuclear Information System (INIS)

    Pindor, M.

    1984-01-01

    The effective Hamiltonian of the model space perturbation theory (multilevel Rayleigh-Schroedinger theory) is expressed as an operator continued fraction. In the case of a nondegenerate model space the expression becomes an operator branched continued fraction. The method is applied to the harmonic oscillator with the kinetic energy treated as the perturbation and to the anharmonic oscillator

  8. Semi-bounded partial differential operators

    CERN Document Server

    Cialdea, Alberto

    2014-01-01

    This book examines the conditions for the semi-boundedness of partial differential operators, which are interpreted in different ways. For example, today we know a great deal about L2-semibounded differential and pseudodifferential operators, although their complete characterization in analytic terms still poses difficulties, even for fairly simple operators. In contrast, until recently almost nothing was known about analytic characterizations of semi-boundedness for differential operators in other Hilbert function spaces and in Banach function spaces. This book works to address that gap. As such, various types of semi-boundedness are considered and a number of relevant conditions which are either necessary and sufficient or best possible in a certain sense are presented. The majority of the results reported on are the authors’ own contributions.

  9. Inequalities Involving Upper Bounds for Certain Matrix Operators

    Indian Academy of Sciences (India)

    Home; Journals; Proceedings – Mathematical Sciences; Volume 116; Issue 3. Inequalities Involving Upper Bounds for Certain Matrix Operators. R Lashkaripour D Foroutannia. Volume ... Keywords. Inequality; norm; summability matrix; Hausdorff matrix; Hilbert matrix; weighted sequence space; Lorentz sequence space.

  10. Diagonalization of Bounded Linear Operators on Separable Quaternionic Hilbert Space

    International Nuclear Information System (INIS)

    Feng Youling; Cao, Yang; Wang Haijun

    2012-01-01

    By using the representation of its complex-conjugate pairs, we have investigated the diagonalization of a bounded linear operator on separable infinite-dimensional right quaternionic Hilbert space. The sufficient condition for diagonalizability of quaternionic operators is derived. The result is applied to anti-Hermitian operators, which is essential for solving Schroedinger equation in quaternionic quantum mechanics.

  11. Improved Rosen's conditions on bound states of Schroedinger operators

    International Nuclear Information System (INIS)

    Exner, P.

    1984-01-01

    We derive a necessary condition on a Schroedinger operator H=-Δ+V on Lsup(2)(Rsup(d)), d>=3 to have a bound state below a given energy epsilon, and a lower bound to the ground-state energy of H. These conditions are expressed in terms of the potential V alone, and generalize the recent results of Rosen to the dimensions d>3 and to the potentials that are not necessarily rapidly decreasing. Some examples are given

  12. Determining Bounds on Assumption Errors in Operational Analysis

    Directory of Open Access Journals (Sweden)

    Neal M. Bengtson

    2014-01-01

    Full Text Available The technique of operational analysis (OA is used in the study of systems performance, mainly for estimating mean values of various measures of interest, such as, number of jobs at a device and response times. The basic principles of operational analysis allow errors in assumptions to be quantified over a time period. The assumptions which are used to derive the operational analysis relationships are studied. Using Karush-Kuhn-Tucker (KKT conditions bounds on error measures of these OA relationships are found. Examples of these bounds are used for representative performance measures to show limits on the difference between true performance values and those estimated by operational analysis relationships. A technique for finding tolerance limits on the bounds is demonstrated with a simulation example.

  13. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  14. Operating US power reactors

    International Nuclear Information System (INIS)

    Silver, E.G.

    1988-01-01

    This update, which appears regularly in each issue of Nuclear Safety, surveys the operations of those power reactors in the US which have been issued operating licenses. Table 1 shows the number of such reactors and their net capacities as of September 30, 1987, the end of the three-month period covered in this report. Table 2 lists the unit capacity and forced outage rate for each licensed reactor for each of the three months (July, August, and September 1987) covered in this report and the cumulative values of these parameters since the beginning of commercial operation. In addition to the tabular data, this article discusses other significant occurrences and developments that affected licensed US power reactors during this reporting period. Status changes at Braidwood Unit 1, Nine Mile Point 2, and Beaver Valley 2 are discussed. Other occurrences discussed are: retraining of control-room operators at Peach Bottom; a request for 25% power for Shoreham, problems at Fermi 2 which delayed the request to go to 75% power; the results of a safety study of the N Reactor at Hanford; a proposed merger of Pacific Gas and Electric with Sacramento Municipal Utility District which would result in the decommissioning of Rancho Seco; the ordered shutdown of Oyster Creek; a minor radioactivity release caused by a steam generator tube rupture at North Anna 1; and 13 fines levied by the NRC on reactor licensees

  15. Some problems in operator theory on bounded symmetric domains

    Czech Academy of Sciences Publication Activity Database

    Engliš, Miroslav

    2004-01-01

    Roč. 81, č. 1 (2004), s. 51-71 ISSN 0167-8019. [Representations of Lie groups, harmonic analysis on homogeneous spaces and quantization. Leiden, 07.12.2002-13.12.2002] R&D Projects: GA ČR GA201/03/0041 Institutional research plan: CEZ:AV0Z1019905 Keywords : homogeneous multiplication operators * bounded symmetric domains Subject RIV: BA - General Mathematics Impact factor: 0.354, year: 2004

  16. Wireless Power Control for Tactical MANET: Power Rate Bounds

    Science.gov (United States)

    2016-09-01

    J; P. Hande; T. Lan; C. W. Tan [2008] Power Control in Cellular Networks, Now Publishers Inc., Hanover, MA. 12. Chaves, Fabiano de Sousa; F. R. P...Asymptotically Fast Convergence, IEEE Selected Areas in Communications, 18(3). 36. Jian, Tao; Nicholas D. Sidiropoulos; Georgios B. Giannakis [2003] Kalman...Power Control and Its Imperfections in CDMA Cellular Systems, IEEE Transactions on Vehicular Technologies, 48, pages 1706–1777. 75. Tan , Chee Wei

  17. Dynamical sampling and frame representations with bounded operators

    DEFF Research Database (Denmark)

    Christensen, Ole; Hasannasab, Marzieh; Rashidi, Ehsan

    2017-01-01

    The purpose of this paper is to study frames for a Hilbert space H, having the form {Tnφ}n=0∞ for some φ∈H and an operator T:H→H. We characterize the frames that have such a representation for a bounded operator T, and discuss the properties of this operator. In particular, we prove that the image...... chain of T has finite length N in the overcomplete case; furthermore {Tnφ}n=0∞ has the very particular property that {Tnφ}n=0N−1∪{Tnφ}n=N+ℓ∞ is a frame for H for all ℓ∈N0. We also prove that frames of the form {Tnφ}n=0∞ are sensitive to the ordering of the elements and to norm...

  18. Bounds on the power of proofs and advice in general physical theories.

    Science.gov (United States)

    Lee, Ciarán M; Hoban, Matty J

    2016-06-01

    Quantum theory presents us with the tools for computational and communication advantages over classical theory. One approach to uncovering the source of these advantages is to determine how computation and communication power vary as quantum theory is replaced by other operationally defined theories from a broad framework of such theories. Such investigations may reveal some of the key physical features required for powerful computation and communication. In this paper, we investigate how simple physical principles bound the power of two different computational paradigms which combine computation and communication in a non-trivial fashion: computation with advice and interactive proof systems. We show that the existence of non-trivial dynamics in a theory implies a bound on the power of computation with advice. Moreover, we provide an explicit example of a theory with no non-trivial dynamics in which the power of computation with advice is unbounded. Finally, we show that the power of simple interactive proof systems in theories where local measurements suffice for tomography is non-trivially bounded. This result provides a proof that [Formula: see text] is contained in [Formula: see text], which does not make use of any uniquely quantum structure-such as the fact that observables correspond to self-adjoint operators-and thus may be of independent interest.

  19. Scalability under a Power Bound using the GREMLINs Framework

    International Nuclear Information System (INIS)

    Maiterth, Matthias

    2015-01-01

    With the move towards exascale, system and software developers will have to deal with issues of extreme parallelism. The system properties affected most by the increase in node and core count are the shared resources on node and across the system. The increase in parallelism leads to reduced memory and bandwidth when regarding individual cores. Since power is a limiting factor for supercomputers, and power is not fully utilized in current systems, overprovisioning compute resources is a viable approach to maximized power utilization. To maximize system performance in regard to these changing conditions, it is necessary to understand how resource restrictions impact performance and system behavior. For the purpose of understanding anticipated system properties the GREMLINs Framework was developed. The framework gives the opportunity to add power restrictions, hinder memory properties and introduce faults to study resilience, among others. These features give the opportunity to use current petascale technology to study problems system designers and software developers will have to face when moving towards exascale and beyond. This work describes the initial release of the GREMLINs Framework, developed for this work, and shows how it can be used to study the scaling behavior of proxy applications. These proxy applications represent a selection of HPC workloads important to the scientific community. The proxy applications studied are AMG2013, an algebraic multi-grid linear system solver, CoMD, a classical molecular dynamics proxy application and NEKBONE, an application that uses a high order spectral element method to solve the Navier-Stokes equations. The main interest of these studies lies in analysis regarding their power behavior at scale under a power bound. These findings show how the GREMLINs Framework can help systems and software designers to attain better application performance and can also be used as basis for CPU power balancing tools to use power more

  20. Scalability under a Power Bound using the GREMLINs Framework

    Energy Technology Data Exchange (ETDEWEB)

    Maiterth, Matthias [Ludwig Maximilian Univ., Munich (Germany)

    2015-02-16

    With the move towards exascale, system and software developers will have to deal with issues of extreme parallelism. The system properties affected most by the increase in node and core count are the shared resources on node and across the system. The increase in parallelism leads to reduced memory and bandwidth when regarding individual cores. Since power is a limiting factor for supercomputers, and power is not fully utilized in current systems, overprovisioning compute resources is a viable approach to maximized power utilization. To maximize system performance in regard to these changing conditions, it is necessary to understand how resource restrictions impact performance and system behavior. For the purpose of understanding anticipated system properties the GREMLINs Framework was developed. The framework gives the opportunity to add power restrictions, hinder memory properties and introduce faults to study resilience, among others. These features give the opportunity to use current petascale technology to study problems system designers and software developers will have to face when moving towards exascale and beyond. This work describes the initial release of the GREMLINs Framework, developed for this work, and shows how it can be used to study the scaling behavior of proxy applications. These proxy applications represent a selection of HPC workloads important to the scientific community. The proxy applications studied are AMG2013, an algebraic multi-grid linear system solver, CoMD, a classical molecular dynamics proxy application and NEKBONE, an application that uses a high order spectral element method to solve the Navier-Stokes equations. The main interest of these studies lies in analysis regarding their power behavior at scale under a power bound. These findings show how the GREMLINs Framework can help systems and software designers to attain better application performance and can also be used as basis for CPU power balancing tools to use power more

  1. Power generation assets. Energy constraints, upper bounds and hedging strategies

    Energy Technology Data Exchange (ETDEWEB)

    Enge, Thomas

    2010-09-20

    The overall topic of this thesis is the valuation of power generation assets under energy and risk constraints. Our focus is on the modeling aspect i.e. to find the right balance between accuracy and computational feasibility. We define a new not yet investigated unit commitment problem that introduces an energy constraint to a thermal power plant. We define a continuous stochastic dynamic program with a nested mixed integer program (MIP). We introduce a fast implementation approach by replacing the MIP with an efficient matrix calculation and use principal component analysis to reduce the number of risk factors. We also provide a fast heuristic valuation approach for comparison. As both models can only provide lower bounds of the asset value, we investigate the theory of upper bounds for a proper validation of our power plant results. We review the primal dual algorithm for swing options by Meinshausen and Hambly and in particular clarify their notation and implementation. Then we provide an extension for swing options with multiple exercises at the same stage that we developed together with Prof. Bender, University of Braunschweig. We outline Prof. Bender's proof and describe the implementation in detail. Finally we provide a risk analysis for our thermal power plant. In particular we investigate strategies to reduce spot price risk to which power plants are significantly exposed. First, we focus on the measurement of spot price risk and propose three appropriate risk figures (Forward delta as opposed to Futures delta, synthetic spot delta and Earnings-at-Risk) and illustrate their application using a business case. Second we suggest risk mitigation strategies for both periods, before and in delivery. The latter tries to alter the dispatch policy i.e. pick less risky hours and accept a (desirably only slightly) smaller return. We introduce a benchmark that weighs risk versus return and that we will call EaR-efficient option value. We propose a mitigation

  2. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

    The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

  3. Operation of nuclear power plants

    International Nuclear Information System (INIS)

    Severa, P.

    1988-04-01

    The textbook for training nuclear power plant personnel is centred on the most important aspects of operating modes of WWER-440 reactors. Attention is devoted to the steady state operation of the unit, shutdown, overhaul with refuelling, physical and power start-up. Also given are the regulations of shift operation and the duties of individual categories of personnel during the shift and during the change of shifts. (Z.M.). 3 figs., 1 tab

  4. Tendencies in operating power reactors

    International Nuclear Information System (INIS)

    Brinckmann, H.F.

    1987-01-01

    A survey is given about new tendencies in operating power reactors. In order to meet the high demands for control and monitoring of power reactors modern procedures are applicated such as the incore-neutron flux detection by means of electron emission detectors and multi-component activation probes, the noise diagnostics as well as high-efficient automation systems

  5. Multiple-Pulse Operation and Bound States of Solitons in Passive Mode-Locked Fiber Lasers

    Directory of Open Access Journals (Sweden)

    A. Komarov

    2012-01-01

    Full Text Available We present results of our research on a multiple-pulse operation of passive mode-locked fiber lasers. The research has been performed on basis of numerical simulation. Multihysteresis dependence of both an intracavity energy and peak intensities of intracavity ultrashort pulses on pump power is found. It is shown that the change of a number of ultrashort pulses in a laser cavity can be realized by hard as well as soft regimes of an excitation and an annihilation of new solitons. Bound steady states of interacting solitons are studied for various mechanisms of nonlinear losses shaping ultrashort pulses. Possibility of coding of information on basis of soliton trains with various bonds between neighboring pulses is discussed. The role of dispersive wave emitted by solitons because of lumped intracavity elements in a formation of powerful soliton wings is analyzed. It is found that such powerful wings result in large bounding energies of interacting solitons in steady states. Various problems of a soliton interaction in passive mode-locked fiber lasers are discussed.

  6. Optimization of power system operation

    CERN Document Server

    Zhu, Jizhong

    2015-01-01

    This book applies the latest applications of new technologies topower system operation and analysis, including new and importantareas that are not covered in the previous edition. Optimization of Power System Operation covers both traditional andmodern technologies, including power flow analysis, steady-statesecurity region analysis, security constrained economic dispatch,multi-area system economic dispatch, unit commitment, optimal powerflow, smart grid operation, optimal load shed, optimalreconfiguration of distribution network, power system uncertaintyanalysis, power system sensitivity analysis, analytic hierarchicalprocess, neural network, fuzzy theory, genetic algorithm,evolutionary programming, and particle swarm optimization, amongothers. New topics such as the wheeling model, multi-areawheeling, the total transfer capability computation in multipleareas, are also addressed. The new edition of this book continues to provide engineers andac demics with a complete picture of the optimization of techn...

  7. Sliding Mode Control for Pressurized-Water Nuclear Reactors in load following operations with bounded xenon oscillations

    International Nuclear Information System (INIS)

    Ansarifar, G.R.; Saadatzi, S.

    2015-01-01

    Highlights: • We present SMC which is a robust nonlinear controller to control the PWR power. • Xenon oscillations are kept bounded within acceptable limits. • The stability analysis has been based on Lyapunov approach. • Simulation results indicate the high performance of this new control. - Abstract: One of the important operations in nuclear power plants is load-following in which imbalance of axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation considered to be a constraint for the load-following operation. In this paper, sliding mode control (SMC) which is a robust nonlinear controller is designed to control the Pressurized-Water Nuclear Reactor (PWR) power for the load-following operation problem that ensures xenon oscillations are kept bounded within acceptable limits. The proposed controller uses constant axial offset (AO) strategy to maintain xenon oscillations to be bounded. The constant AO is a robust state constraint for load-following problem. The reactor core is simulated based on the two-point nuclear reactor model and one delayed neutron group. The stability analysis is given by means Lyapunov approach, thus the control system is guaranteed to be stable within a large range. The employed method is easy to implement in practical applications and moreover, the sliding mode control exhibits the desired dynamic properties during the entire output-tracking process independent of perturbations. Simulation results are presented to demonstrate the effectiveness of the proposed controller in terms of performance, robustness and stability. Results show that the proposed controller for the load-following operation is sufficiently effective so that the xenon oscillations are kept bounded in the considered region

  8. Efficient compliance with prescribed bounds on operational parameters by means of hypothesis testing using reactor data

    International Nuclear Information System (INIS)

    Sermer, P.; Olive, C.; Hoppe, F.M.

    2000-01-01

    - A common problem in any reactor operations is to comply with a requirement that certain operational parameters are constrained to lie within some prescribed bounds. The fundamental issue which is to be addressed in any compliance description can be stated as follows: The compliance definition, compliance procedures and allowances for uncertainties in data and accompanying methodologies, should be well defined and justifiable. To this end, a mathematical framework for compliance, in which the computed or measured estimates of process parameters are considered random variables, is described in this paper. This allows a statistical formulation of the definition of compliance with licence or otherwise imposed limits. An important aspect of the proposed methodology is that the derived statistical tests are obtained by a Monte Carlo procedure using actual reactor operational data. The implementation of the methodology requires a routine surveillance of the reactor core in order to perform the underlying statistical tests. The additional work required for surveillance is balanced by the fact that the resulting actions on the reactor operations, implemented in station procedures, make the reactor 'safer' by increasing the operating margins. Furthermore, increased margins are also achieved by efficient solution techniques which may allow an increase in reactor power. A rigorous analysis of a compliance problem using statistical hypothesis testing based on extreme value probability distributions and actual reactor operational data leads to effective solutions in the areas of licensing, nuclear safety, reliability and competitiveness of operating nuclear reactors. (author)

  9. Linear inequalities and overlap bounds: a novel use of an operator inequality

    International Nuclear Information System (INIS)

    Cohen, M.; Leopold, J.G.

    1976-01-01

    Bounds to overlap integrals are obtained by an operator inequality technique. The formulation involves a set of linear inequalities with several overlap integrals as unknowns. The 'solution' of this set of inequalities leads to bound expressions which complement those of other workers. (author)

  10. Organizing nuclear power plant operation

    International Nuclear Information System (INIS)

    Adams, H.W.; Rekittke, K.

    1987-01-01

    With the preliminary culmination in the convoy plants of the high standard of engineered safeguards in German nuclear power plants developed over the past twenty years, the interest of operators has now increasingly turned to problems which had not been in the focus of attention before. One of these problems is the organization of nuclear power plant operation. In order to enlarge the basis of knowledge, which is documented also in the rules published by the Kerntechnischer Ausschuss (Nuclear Technology Committee), the German Federal Minister of the Interior has commissioned a study of the organizational structures of nuclear power plants. The findings of that study are covered in the article. Two representative nuclear power plants in the Federal Republic of Germany were selected for the study, one of them a single-unit plant run by an independent operating company in the form of a private company under German law (GmbH), the other a dual-unit plant operated as a dependent unit of a utility. The two enterprises have different structures of organization. (orig.) [de

  11. Compact composition operators on real Banach spaces of complex-valued bounded Lipschitz functions

    Directory of Open Access Journals (Sweden)

    Davood Alimohammadi

    2014-10-01

    Full Text Available We characterize compact composition operators on real Banachspaces of complex-valued bounded Lipschitz functions on metricspaces, not necessarily compact, with Lipschitz involutions anddetermine their spectra.

  12. Estimation of uncertainty bounds for the future performance of a power plant

    DEFF Research Database (Denmark)

    Odgaard, Peter Fogh; Stoustrup, Jakob

    2009-01-01

    on recent data and the other is based on operating points as well. The third proposed scheme uses dynamical models of the prediction uncertainties, like in H-infinity-control. The proposed schemes are subsequently applied to experimental data from a coal-fired power plant. {Two sets of data from an actual......} the future performance of these plants is that available models of the plants are uncertain. In this paper three schemes for predicting uncertain dynamical systems are presented. The schemes estimate upper and lower bounds on the system performance. Two of the schemes are statistically based, one only based......Prediction of the future performance of large-scale power plants can be very relevant for the operators of these plants, as the predictions can indicate possible problems or failures due to current operating conditions and/or future possible operating conditions. {A problem in predicting...

  13. On Pták functions for bounded operators

    Directory of Open Access Journals (Sweden)

    Abdellah El Kinani

    2014-10-01

    Full Text Available The purpose of this paper is to prove that if the Pták function p is an operator norm, on \\mathcal{B}(E, associated to a norm | . |, then (E, | . | is a pseudo-Hilbert space. As a consequence, we obtain that if \\mathcal{B}(E  is a C*-algebra, then E is a Hilbert space.

  14. Uniform bounds of the spectrum of Dirac operators

    International Nuclear Information System (INIS)

    Ezin, J.P.; Rigoli, M.

    1988-06-01

    Let (M,g) be a compact, connected Riemannian manifold of dimension n ≥ 3. We denote with Ric g , S g and γ the Ricci curvature, the scalar curvature and conformal class of g, respectively. Then using techniques introduced by A. Lichnerowicz we present a proof of Hijazi's following result. If S g ≥ 0 and (M,g) is a spin manifold, there is a constant μ ≥ 0, depending only on n and γ, such that every eigenvalue λ of the Dirac operator acting on spinor fields over M satisfies λ 2 vol(M,g) 2/n ≥μ. In an appendix we prove that if S g is constant and (M,g) is not conformally diffeomorphic to a standard n-sphere, then if γ contains another metric with constant scalar curvature, there is a positive function ρ on M such that (Ric - Sg / n g) (∇ρ, ∇ρ) is negative somewhere on M. (author). 12 refs

  15. Operational power reactor health physics

    International Nuclear Information System (INIS)

    Watson, B.A.

    1987-01-01

    Operational Health Physics can be comprised of a multitude of organizations, both corporate and at the plant sites. The following discussion centers around Baltimore Gas and Electric's (BG and E) Calvert Cliffs Nuclear Power Plant, located in Lusby, Maryland. Calvert Cliffs is a twin Combustion Engineering 825 MWe pressurized water reactor site with Unit I having a General electric turbine-generator and Unit II having a Westinghouse turbine-generator. Having just completed each Unit's ten-year Inservice Inspection and Refueling Outge, a total of 20 reactor years operating health physics experience have been accumulated at Calvert Cliffs. Because BG and E has only one nuclear site most health physics functions are performed at the plant site. This is also true for the other BG and E nuclear related organizations, such as Engineering and Quality Assurance. Utilities with multiple plant sites have corporate health physics entity usually providing oversight to the various plant programs

  16. 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...

  17. 47 CFR 73.751 - Operating power.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Operating power. 73.751 Section 73.751... International Broadcast Stations § 73.751 Operating power. No international broadcast station shall be authorized to install, or be licensed for operation of, transmitter equipment with: (a) A rated carrier power...

  18. Operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Ackermann, G.

    1987-01-01

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

  19. A lower bound on the relative error of mixed-state cloning and related operations

    International Nuclear Information System (INIS)

    Rastegin, A E

    2003-01-01

    We extend the concept of the relative error to mixed-state cloning and related physical operations, in which the ancilla contains some information a priori about the input state. The lower bound on the relative error is obtained. It is shown that this result provides further support for a stronger no-cloning theorem

  20. On the bound states of Schrodinger operators with -interactions on conical surfaces

    Czech Academy of Sciences Publication Activity Database

    Lotoreichik, Vladimir; Ourmieres-Bonafos, T.

    2016-01-01

    Roč. 41, č. 6 (2016), s. 999-1028 ISSN 0360-5302 Institutional support: RVO:61389005 Keywords : conical and hyperconical surfaces * delta-interaction * existence of bound states * Schrodinger operator * spectral asymptotics Subject RIV: BE - Theoretical Physics Impact factor: 1.608, year: 2016

  1. A closed graph theorem for order bounded operators | Harm van der ...

    African Journals Online (AJOL)

    ... theory to prove a version of the closed graph theorem for order bounded operators on Archimedean vector lattices. This illustrates the usefulness of convergence spaces in dealing with problems in vector lattice theory, problems that may fail to be amenable to the usual Hausdorff-Kuratowski-Bourbaki concept of topology.

  2. Formulae and Bounds connected to Optimal Design and Homogenization of Partial Differential Operators and Integral Functionals

    Energy Technology Data Exchange (ETDEWEB)

    Lukkassen, D.

    1996-12-31

    When partial differential equations are set up to model physical processes in strongly heterogeneous materials, effective parameters for heat transfer, electric conductivity etc. are usually required. Averaging methods often lead to convergence problems and in homogenization theory one is therefore led to study how certain integral functionals behave asymptotically. This mathematical doctoral thesis discusses (1) means and bounds connected to homogenization of integral functionals, (2) reiterated homogenization of integral functionals, (3) bounds and homogenization of some particular partial differential operators, (4) applications and further results. 154 refs., 11 figs., 8 tabs.

  3. The asymptotic behavior of Frobenius-Perron operator with local lower-bound function

    International Nuclear Information System (INIS)

    Ding Yiming

    2003-01-01

    Let (X,Σ,μ) be a σ-finite measure space, S:X→X be a nonsingular transformation and P S :L 1 →L 1 be the Frobenius-Perron operator associated with S. It is proved that if P S satisfies the local lower-bound function condition then for every f is a subset of D the sequence {P S n f} converges strongly to a stationary density of P S as n→∞. The statistical stability of S is also concerned via the local lower-bound function method

  4. Simulators predict power plant operation

    Energy Technology Data Exchange (ETDEWEB)

    Peltier, R.

    2002-07-01

    Mix the complexity of a new construction or major retrofit project with today's 'do more with less', a pinch of 'personnel inexperience,' and a dash of 'unintended consequences', and you have got a recipe for insomnia. Advanced simulation tools, however, can help you wring out your design train your operators before the first wire is terminated and just may be get a good night's rest. The article describes several examples of uses of simulation tools. Esscor recently completed a simulation project for a major US utility exploring the potential for furnace/duct implosion that could result from adding higher volumetric flow induced-draft fans and selective catalytic reduction to a 650-MW coal-fired plant. CAF Electronics Inc. provided a full-scope simulator for Alstom's KA24-1 combined-cycle power plant in Paris, France. Computational fluid dynamics (CFD) tools are being used by the Gas Technology Institute to simulate the performance of the next generation of pulverized coal combustors. 5 figs.

  5. Some simple conditions of bound states of Schroedinger operators in dimension d >= 3

    International Nuclear Information System (INIS)

    Exner, P.

    1984-01-01

    A necessary condition for existence of bound states below a given energy of a Schroedinger operator H=-Δ+V on L 2 (Rsup(d)), d>=3, together with a lower bound to the ground-state energy of H are derived using the Sobolev inequalities. It generalizes some recent results to the dimensions d>3 and to the potentials that are not necessarily rapidly decreasing. Comparison to other known necessary conditions is given. The examples of the d-dimensional hydrogen-like atom and the d-dimensional harmonic oscillator are discussed. In both of them the bound to the ground-state energy becomes remarkably tight for large values of d

  6. New approximation to the bound states of Schroedinger operators with coulomb interaction

    International Nuclear Information System (INIS)

    Nunez, M.A.; Izquierdo B., G.

    1994-01-01

    In this work, the authors present a mathematical formulation of the physical fact that the bound states of a quantum system confined into a box Ω (with impenetrable walls) are similar to those of the unconfined system, if the box Ω is sufficiently large, and it is shown how the bound states of atomic and molecular Hamiltonians can be approximated by those of the system confined for a box Ω large enough (Dirichlet eigenproblem in Ω). Thus, a method for computing bound states is obtained which has the advantage of reducing the problem to the case of compact operators. This implies that a broad class of numerical and analytic techniques used for solving the Dirichlet problem, may be applied in full strength to obtain accurate computations of energy levels, wave functions, and other physical properties of interest

  7. Tight upper bound for the maximal quantum value of the Svetlichny operators

    Science.gov (United States)

    Li, Ming; Shen, Shuqian; Jing, Naihuan; Fei, Shao-Ming; Li-Jost, Xianqing

    2017-10-01

    It is a challenging task to detect genuine multipartite nonlocality (GMNL). In this paper, the problem is considered via computing the maximal quantum value of Svetlichny operators for three-qubit systems and a tight upper bound is obtained. The constraints on the quantum states for the tightness of the bound are also presented. The approach enables us to give the necessary and sufficient conditions of violating the Svetlichny inequality (SI) for several quantum states, including the white and color noised Greenberger-Horne-Zeilinger (GHZ) states. The relation between the genuine multipartite entanglement concurrence and the maximal quantum value of the Svetlichny operators for mixed GHZ class states is also discussed. As the SI is useful for the investigation of GMNL, our results give an effective and operational method to detect the GMNL for three-qubit mixed states.

  8. Optimization Criteria of Power Transformer Operation

    Directory of Open Access Journals (Sweden)

    A. A. Gonchar

    2006-01-01

    Full Text Available It has been shown that minimum losses in active power of a power transformer do not correspond to its maximum efficiency. For a transformer being operated there are no so called «zones of its economical operation». In this case strictly specified value of active power losses corresponds to a particular current of the winding.

  9. Nuclear power plant operational data compilation system

    International Nuclear Information System (INIS)

    Silberberg, S.

    1980-01-01

    Electricite de France R and D Division has set up a nuclear power plant operational data compilation system. This data bank, created through American documents allows results about plant operation and operational material behaviour to be given. At present, French units at commercial operation are taken into account. Results obtained after five years of data bank operation are given. (author)

  10. A Note on the G-Cyclic Operators over a Bounded Semigroup

    International Nuclear Information System (INIS)

    Hamada, Nuha H.; Jamil, Zeana Z.

    2010-08-01

    Let H be an infinite-dimensional separable complex Hilbert space, and B(H) be the Banach algebra of all linear bounded operators on H. Let S be a multiplication semigroup of C with 1, an operator T element of B(H) is called G-cyclic operator over S if there is a vector x in H such that {αT n x|α element of S, n ≥ 0} is dense in H. In this case x is called a G-cyclic vector for T over S. If T is G-cyclic operator and S = {1} then T is a hypercyclic operator. In this paper, we study the spectral properties of a G-cyclic operators over a bounded S under the condition that zero is not in the closure of S. We show that the class of all G-cyclic operators is contained in the norm-closure of the class of all hypercyclic operators. (author)

  11. Thermal power plant design and operation

    CERN Document Server

    Sarkar, Dipak

    2015-01-01

    Thermal Power Plant: Design and Operation deals with various aspects of a thermal power plant, providing a new dimension to the subject, with focus on operating practices and troubleshooting, as well as technology and design. Its author has a 40-long association with thermal power plants in design as well as field engineering, sharing his experience with professional engineers under various training capacities, such as training programs for graduate engineers and operating personnel. Thermal Power Plant presents practical content on coal-, gas-, oil-, peat- and biomass-fueled thermal power

  12. The operation of nuclear power plants

    International Nuclear Information System (INIS)

    Brosche, D.

    1992-01-01

    The duties to be performed in managing the operation of a nuclear power plant are highly diverse, as will be explained in this contribution by the examples of the Grafenrheinfeld Nuclear Power Station. The excellent safety record and the high availabilities of German nuclear power plants demonstrate that their operators have adopted the right approaches. Systematic evaluation of the operating experience accumulated inhouse and in other plants is of great significance in removing weak spots and improving operation. The manifold and complex activities in the structure of organization and of activities in a nuclear power plant require a high degree of division of labor. (orig.) [de

  13. Power generation, operation and control

    CERN Document Server

    Wood, Allen J; Sheblé, Gerald B

    2013-01-01

    Since publication of the second edition, there have been extensive changes in the algorithms, methods, and assumptions in energy management systems that analyze and control power generation. This edition is updated to acquaint electrical engineering students and professionals with current power generation systems. Algorithms and methods for solving integrated economic, network, and generating system analysis are provided. Also included are the state-of-the-art topics undergoing evolutionary change, including market simulation, multiple market analysis, multiple interchange contract analysis, c

  14. The continuous spectrum and the effect of parametric resonance. The case of bounded operators

    International Nuclear Information System (INIS)

    Skazka, V V

    2014-01-01

    The paper is concerned with the Mathieu-type differential equation u ″ =−A 2 u+εB(t)u in a Hilbert space H. It is assumed that A is a bounded self-adjoint operator which only has an absolutely continuous spectrum and B(t) is almost periodic operator-valued function. Sufficient conditions are obtained under which the Cauchy problem for this equation is stable for small ε and hence free of parametric resonance. Bibliography: 10 titles

  15. Operational safety of nuclear power plants

    International Nuclear Information System (INIS)

    Tanguy, P.

    1987-01-01

    The operational safety of nuclear power plants has become an important safety issue since the Chernobyl accident. A description is given of the various aspects of operational safety, including the importance of human factors, responsibility, the role and training of the operator, the operator-machine interface, commissioning and operating procedures, experience feedback, and maintenance. The lessons to be learnt from Chernobyl are considered with respect to operator errors and the management of severe accidents. Training of personnel, operating experience feedback, actions to be taken in case of severe accidents, and international cooperation in the field of operational safety, are also discussed. (U.K.)

  16. The number of bound states for a discrete Schroedinger operator on ZN, N≥1, lattices

    International Nuclear Information System (INIS)

    Karachalios, N I

    2008-01-01

    We consider the discrete Schroedinger operator -Δ d +U in Z N , N≥1 in the case of a potential with negative part in an appropriate l σ -space (decays with an appropriate rate). We present a discrete analog of the method of Li and Yau (1983 Commun. Math. Phys. 88 309-18), proving an explicit upper estimate on the number of bound states N d (0)={j:μ j ≤0}, which is independent of the dimension of the lattice. This is a major difference with the continuous counterpart estimate, which is not valid when N = 1, 2. As a consequence, a dimension-independent smallness criterion for the existence of bound states is derived in contrast to the continuous case as well as to the discrete case of vanishing potential. A short comment is made on possible applications of the results to the study of the dynamics of some particular spatially discrete nonlinear systems

  17. Computation of Lie transformations from a power series: Bounds and optimum truncation

    International Nuclear Information System (INIS)

    Gjaja, I.

    1996-01-01

    The problem considered is the computation of an infinite product (composition) of Lie transformations generated by homogeneous polynomials of increasing order from a given asymptotic power series. Bounds are computed for the infinitesimal form of the Lie transformations and for the domain of analyticity of the first n of them. Even when the power series is convergent, the estimates exhibit a factorial-type growth, and thus do not guarantee convergence of the product. The optimum truncation is determined by minimizing the remainder after the first n Lie transformations have been applied

  18. Fractional power operation of tokamak reactors

    International Nuclear Information System (INIS)

    Mau, T.K.; Vold, E.L.; Conn, R.W.

    1986-01-01

    Methods to operate a tokamak fusion reactor at fractions of its rated power, identify the more effective control knobs and assess the impact of the requirements of fractional power operation on full power reactor design are explored. In particular, the role of burn control in maintaining the plasma at thermal equilibrium throughout these operations is studied. As a prerequisite to this task, the critical physics issues relevant to reactor performance predictions are examined and some insight into their impact on fractional power operation is offered. The basic tool of analysis consists of a zero-dimensional (0-D) time-dependent plasma power balance code which incorporates the most advanced data base and models in transport and burn plasma physics relevant to tokamaks. Because the plasma power balance is dominated by the transport loss and given the large uncertainty in the confinement model, the authors have studied the problem for a wide range of energy confinement scalings. The results of this analysis form the basis for studying the temporal behavior of the plasma under various thermal control mechanisms. Scenarios of thermally stable full and fractional power operations have been determined for a variety of transport models, with either passive or active feedback burn control. Important power control parameters, such as gas fueling rate, auxiliary power and other plasma quantities that affect transport losses, have also been identified. The results of these studies vary with the individual transport scaling used and, in particular, with respect to the effect of alpha heating power on confinement

  19. Unmanned operation of Hydro Power Plants

    International Nuclear Information System (INIS)

    Regula, E.

    2008-01-01

    Intentions to launch unmanned operation are no news, the very first occurred in Hydro Power Plants (HPP) at the time when the first computer technology was implemented into process of power generation, i.e. no later than in 1960 s . ENEL entering Slovenske elektrarne not only revived but significantly accelerated the implementation process of unmanned operation. Experience of ENEL says that unmanned operation means better reliability of the HPP and this is the priority. (author)

  20. Power System Operation with Large Scale Wind Power Integration

    DEFF Research Database (Denmark)

    Suwannarat, A.; Bak-Jensen, B.; Chen, Z.

    2007-01-01

    to the uncertain nature of wind power. In this paper, proposed models of generations and control system are presented which analyze the deviation of power exchange at the western Danish-German border, taking into account the fluctuating nature of wind power. The performance of the secondary control of the thermal......The Danish power system starts to face problems of integrating thousands megawatts of wind power, which produce in a stochastic behavior due to natural wind fluctuations. With wind power capacities increasing, the Danish Transmission System Operator (TSO) is faced with new challenges related...... power plants and the spinning reserves control from the Combined Heat and Power (CHP) units to achieve active power balance with the increased wind power penetration is presented....

  1. Evaluation of nuclear power plant operator's ability

    International Nuclear Information System (INIS)

    Wei Li; He Xuhong; Zhao Bingquan

    2004-01-01

    Based on the quantitative research on nuclear power plant (NPP) operator's psychological characteristics and performance, the Borda's method of fuzzy mathematics combined with the character of operator's task is used to evaluate their abilities. The result provides the reference for operator's reliability research and psychological evaluation. (author)

  2. Training of power plant operating personnel

    International Nuclear Information System (INIS)

    Kraftwerksschule, E.V.

    1986-01-01

    In Germany, professional training of power plant operating personnel became an important issue in the fifties, when power plant parameters as well as complexity of instrumentation and control increased considerably. Working Groups of VGB Technische Vereiningung der Grosskraftwerketreiber e.v. (Association of Large Power Plant Operators) developed a professional career for power plant operating personnel and defined pre-requisites, scope and objectives of training. In 1957 the German utilities founded KRAFTWERKSSCHULE E.V. (kws) as a school for theoretical training and for guidance of practical training in the power plants. KWS is a non-profit organisation and independent of authorities. Today KWS has 127 members in Germany and in 6 other countries. The objectives of KWS include the training of: -Kraftwerker (control room operators; - Kraftwerksmesiter (shift supervisors); and - shift engineers; according the guidelines of the VGB

  3. Operational characteristics of nuclear power plants - modelling of operational safety

    International Nuclear Information System (INIS)

    Studovic, M.

    1984-01-01

    By operational experience of nuclear power plants and realize dlevel of availability of plant, systems and componenst reliabiliuty, operational safety and public protection, as a source on nature of distrurbances in power plant systems and lessons drawn by the TMI-2, in th epaper are discussed: examination of design safety for ultimate ensuring of safe operational conditions of the nuclear power plant; significance of the adequate action for keeping proess parameters in prescribed limits and reactor cooling rquirements; developed systems for measurements detection and monitoring all critical parameters in the nuclear steam supply system; contents of theoretical investigation and mathematical modeling of the physical phenomena and process in nuclear power plant system and components as software, supporting for ensuring of operational safety and new access in staff education process; program and progress of the investigation of some physical phenomena and mathematical modeling of nuclear plant transients, prepared at faculty of mechanical Engineering in Belgrade. (author)

  4. Intelligent operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Morioka, Toshihiko; Fukumoto, Akira; Suto, Osamu; Naito, Norio.

    1987-01-01

    Nuclear power plants consist of many systems and are operated by skillful operators with plenty of knowledge and experience of nuclear plants. Recently, plant automation or computerized operator support systems have come to be utilized, but the synthetic judgment of plant operation and management remains as human roles. Toshiba is of the opinion that the activities (planning, operation and maintenance) should be integrated, and man-machine interface should be human-friendly. We have begun to develop the intelligent operation system aiming at reducing the operator's role within the fundamental judgment through the use of artificial intelligence. (author)

  5. Technical support for nuclear power operations

    International Nuclear Information System (INIS)

    1999-04-01

    This report prepared by the group of senior experts from nuclear operating organizations in Member states, addresses the problem of improving the operating performance of nuclear power plants. Safe and reliable operation is essential for strengthening the viability of nuclear power in the increasingly competitive market of electric power. Basic principles and requirements concerning technical procedures and developed practices are discussed. Report reflects the best current international practices and presents those management initiatives that go beyond the mandated regulatory compliance and could lead to enhancement od operational safety and improved plant performance. By correlating experiences and presenting collective effective practices it is meant to assist nuclear power plant managers in achieving improvement in operation through the contribution of effective technical support

  6. Qualification of nuclear power plant operations personnel

    International Nuclear Information System (INIS)

    1984-01-01

    With the ultimate aim of reducing the possibility of human error in nuclear power plant operations, the Guidebook discusses the organizational aspects, the staffing requirements, the educational systems and qualifications, the competence requirements, the ways to establish, preserve and verify competence, the specific aspects of personnel management and training for nuclear power plant operations, and finally the particular situations and difficulties to be overcome by utilities starting their first nuclear power plant. An important aspect presented in the Guidebook is the experience in training and qualification of nuclear power plant personnel in various countries: Argentina, Belgium, Canada, Czechoslovakia, France, Federal Republic of Germany, Spain, Sweden, United Kingdom and United States of America

  7. Research of the Power Plant Operational Modes

    Directory of Open Access Journals (Sweden)

    Koismynina Nina M.

    2017-01-01

    Full Text Available In this article the algorithm of the power plant operational modes research is offered. According to this algorithm the program for the modes analysis and connection power transformers choice is developed. The program can be used as educational means for studying of the power plant electric part, at the same time basic data are provided. Also the program can be used for the analysis of the working power plants modes. Checks of the entered data completeness and a choice correctness of the operational modes are provided in the program; in all cases of a deviation from the correct decisions to the user the relevant information is given.

  8. Frames of exponentials:lower frame bounds for finite subfamilies, and approximation of the inverse frame operator

    DEFF Research Database (Denmark)

    Christensen, Ole; Lindner, Alexander M

    2001-01-01

    We give lower frame bounds for finite subfamilies of a frame of exponentials {e(i lambdak(.))}k is an element ofZ in L-2(-pi,pi). We also present a method for approximation of the inverse frame operator corresponding to {e(i lambdak(.))}k is an element ofZ, where knowledge of the frame bounds for...

  9. The covariant-evolution-operator method in bound-state QED

    International Nuclear Information System (INIS)

    Lindgren, Ingvar; Salomonson, Sten; Aasen, Bjoern

    2004-01-01

    The methods of quantum-electrodynamical (QED) calculations on bound atomic systems are reviewed with emphasis on the newly developed covariant-evolution-operator method. The aim is to compare that method with other available methods and also to point out possibilities to combine that with standard many-body perturbation theory (MBPT) in order to perform accurate numerical QED calculations, including quasi-degeneracy, also for light elements, where the electron correlation is relatively strong. As a background, the time-independent many-body perturbation theory (MBPT) is briefly reviewed, particularly the method with extended model space. Time-dependent perturbation theory is discussed in some detail, introducing the time-evolution operator and the Gell-Mann-Low relation, generalized to an arbitrary model space. Three methods of treating the bound-state QED problem are discussed. The standard S-matrix formulation, which is restricted to a degenerate model space, is discussed only briefly. Two methods applicable also to the quasi-degenerate problem are treated in more detail, the two-times Green's-function and the covariant-evolution-operator techniques. The treatment is concentrated on the latter technique, which has been developed more recently and which has not been discussed in more detail before. A comparison of the two-times Green's-function and the covariant-evolution-operator techniques, which have great similarities, is performed. In the appendix a simple procedure is derived for expressing the evolution-operator diagrams of arbitrary order. The possibilities of merging QED in the covariant evolution-operator formulation with MBPT in a systematic way is indicated. With such a technique it might be feasible to perform accurate QED calculations also on light elements, which is presently not possible with the techniques available

  10. Universal bounds on spectral measures of one-dimensional Schrödinger operators

    CERN Document Server

    Remling, C

    2002-01-01

    Consider a Schrödinger operator $H=-d^2/dx^2+V(x)$ on $L_2(0,\\infty)$ and suppose that an initial piece of the potential $V(x)$, $0bounds on the spectral measure of intervals with a certain minimum length. This length scale is set by the eigenvalues of the problems on $[0,N]$. So in a sense (and perhaps somewhat surprisingly) the behavior of $V(x)$ becomes less important if $x$ grows. The results of this paper are developments of classical work of Chebyshev and Markov on orthogonal polynomials.

  11. Operator support system for nuclear power plants

    International Nuclear Information System (INIS)

    Mori, Nobuyuki; Tai, Ichiro; Sudo, Osamu; Naito, Norio.

    1987-01-01

    The nuclear power generation in Japan maintains the high capacity factor, and its proportion taken in the total generated electric power exceeded 1/4, thus it has become the indispensable energy source. Recently moreover, the nuclear power plants which are harmonious with operators and easy to operate are demanded. For realizing this, the technical development such as the heightening of operation watching performance, the adoption of automation, and the improvement of various man-machine systems for reducing the burden of operators has been advanced by utilizing electronic techniques. In this paper, the trend of the man-machine systems in nuclear power plants, the positioning of operation support system, the support in the aspects of information, action and knowledge, the example of a new central control board, the operation support system using a computer, an operation support expert system and the problems hereafter are described. As the development of the man-machine system in nuclear power plants, the upgrading from a present new central control board system PODIA through A-PODIA, in which the operational function to deal with various phenomena arising in plants and safety control function are added, to 1-PODIA, in which knowledge engineering technology is adopted, is expected. (Kako, I.)

  12. ALARA for nuclear power plant operation

    International Nuclear Information System (INIS)

    Knapp, P.J.

    1979-01-01

    The concept of maintaining radiation exposures as low as reasonably achievable (ALARA) is outlined in connection with nuclear power plant operations. The basis of the concept is reviewed and a specific example of ALARA action is presented. (author)

  13. Fatigue assessments in operating nuclear power plants

    International Nuclear Information System (INIS)

    Gosselin, S.R.; Deardorff, A.F.; Peltola, D.W.

    1994-01-01

    In November 1991, the ASME Section XI Task Group on Operating Plant Fatigue Assessment was formed to develop criteria and evaluation methodology for evaluating the effects of cyclic operation in operating nuclear power plants. The objective was to develop guidelines for inclusion in Section XI that could be used by plant operators in evaluating fatigue concerns and their impact on serviceability. This paper discusses the work performed by the Task Group. It explores the concept of ''Fatigue Design Basis'' versus ''Fatigue Operating Basis'' by examining the roles of ASME Section III and ASME Section XI in the design and operation of the nuclear power plants. Guidelines are summarized that may help plant operators perform effective design transient cycle evaluations and optimize cycle counting and fatigue usage tracking. The alternative fatigue evaluation approach using flaw tolerance is also introduced

  14. Increase of hydroelectric power plant operation reliability

    International Nuclear Information System (INIS)

    Koshumbaev, M.B.

    2006-01-01

    The new design of the turbine of hydroelectric power plant (HPP) is executed in the form of a pipe with plates. Proposed solution allows increasing the hydroelectric power plant capacity at existing head and water flow. At that time the HPP turbine reliability is increase, its operation performances are improving. Design efficiency is effective mostly for small-scale and micro-HPP due to reliable operation, low-end technology, and harmless ecological application. (author)

  15. Nuclear power plant operating experience, 1976

    International Nuclear Information System (INIS)

    1977-11-01

    This report is the third in a series of reports issued annually that summarize the operating experience of U.S. nuclear power plants in commercial operation. Power generation statistics, plant outages, reportable occurrences, fuel element performance, occupational radiation exposure and radioactive effluents for each plant are presented. Summary highlights of these areas are discussed. The report includes 1976 data from 55 plants--23 boiling water reactor plants and 32 pressurized water reactor plants

  16. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1994-03-01

    In the third quarter of 1993, all of Finland's four nuclear power plant units were in power operation, with the exception of the annual maintenance outages of the Loviisa units. The load factor average of the plant units was 83.6 %. None of the events which occurred during this annual quarter had any bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

  17. Nuclear power plant operation 2016. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2017-05-15

    A report is given on the operating results achieved in 2016, events important to plant safety, special and relevant repair, and retrofit measures from nuclear power plants in Germany. Reports about nuclear power plants in Belgium, Finland, the Netherlands, Switzerland, and Spain will be published in a further issue.

  18. Safe operation of power plants. Pt. 1

    International Nuclear Information System (INIS)

    Freymeyer, P.

    1977-01-01

    Electrotechniques were given a dominating role in the construction of nuclear power plants. The operation of power plants - particularly nuclear power plants - is impossible without the use of electrotechnical and control means. Despite of all reserve in the development and despite of the conservative attitude it is necessary to use the newest results of development and to incite the development ot new electronic systems for the solution of these tasks. (orig.) [de

  19. Analysis Bounding Double Shell Tank (DST) Performance for the Hanford Tank Waste Operation Simulator Case 2

    International Nuclear Information System (INIS)

    SMITH, D.F.

    2002-01-01

    The purpose of this analysis is to compare the latest Tank Farm Contractor Operation and Utilization Plan (HNF-SD-WM-SP-012, Rev. 3) ''Case 2'' operating scenarios with a previous bounding analysis for the Double-Shell Tank (DST) System in order to provide a technical assessment against the current set of DST System performance requirements. A later update to HNF-SD-WM-SP-012 (i.e., Rev. 3A), released in late December 2001, did not impact the results of this analysis. This analysis provides technical support for revising the Performance Requirements for the Double-Shell Tank System, HNF-2168, Rev. 3, used as the basis for defining performance requirements noted in System Specification for the Double-Shell Tank System, HNF-SD-WM-TRD-007. Rev. 1

  20. Highly excited bound-state resonances of short-range inverse power-law potentials

    Energy Technology Data Exchange (ETDEWEB)

    Hod, Shahar [The Ruppin Academic Center, Emeq Hefer (Israel); The Hadassah Academic College, Jerusalem (Israel)

    2017-11-15

    We study analytically the radial Schroedinger equation with long-range attractive potentials whose asymptotic behaviors are dominated by inverse power-law tails of the form V(r) = -β{sub n}r{sup -n} with n > 2. In particular, assuming that the effective radial potential is characterized by a short-range infinitely repulsive core of radius R, we derive a compact analytical formula for the threshold energy E{sub l}{sup max} = E{sub l}{sup max}(n, β{sub n}, R), which characterizes the most weakly bound-state resonance (the most excited energy level) of the quantum system. (orig.)

  1. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1987-01-01

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  2. Operation reports of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    The requirements aiming to standardize the program of nuclear power plant operation report, required by Brazilian Energy Commission - CNEN - to evaluate the activities related to the nuclear technical safety and to the radiation protection during the units operational phase, are showed. (E.G.) [pt

  3. Professional adaptability of nuclear power plant operators

    International Nuclear Information System (INIS)

    He Xuhong; Huang Xiangrui

    2006-01-01

    The paper concerns in the results of analysis for nuclear power plant (NPP) operator job and analysis for human errors related NPP accidents. Based on the principle of ergonomics a full psychological selection system of the professional adaptability of NPP operators including cognitive ability, personality and psychological health was established. The application way and importance of the professional adaptability research are discussed. (authors)

  4. Modeling Control Situations in Power System Operations

    DEFF Research Database (Denmark)

    Saleem, Arshad; Lind, Morten; Singh, Sri Niwas

    2010-01-01

    for intelligent operation and control must represent system features, so that information from measurements can be related to possible system states and to control actions. These general modeling requirements are well understood, but it is, in general, difficult to translate them into a model because of the lack...... of explicit principles for model construction. This paper presents a work on using explicit means-ends model based reasoning about complex control situations which results in maintaining consistent perspectives and selecting appropriate control action for goal driven agents. An example of power system......Increased interconnection and loading of the power system along with deregulation has brought new challenges for electric power system operation, control and automation. Traditional power system models used in intelligent operation and control are highly dependent on the task purpose. Thus, a model...

  5. Method of operating BWR type power plants

    International Nuclear Information System (INIS)

    Koyama, Kazuaki.

    1981-01-01

    Purpose: To improve the operation efficiency of BWR type reactors by reducing the time from the start-up of the reactor to the start-up of the turbine and electrical generator, as well as decrease the pressure difference in each of the sections of the pressure vessel to thereby extend its life span. Method: The operation comprises switching the nuclear reactor from the shutdown mode to the start-up mode, increasing the reactor power to a predetermined level lower than a rated power while maintaining the reactor pressure to a predetermined level lower than a rated pressure, starting up a turbine and an electrical generator in the state of the predetermined reactor pressure and the reactor power to connect the electrical generator to the power transmission system and, thereafter, increasing the reactor pressure and the reactor power to the predetermined rated pressure and rated power respectively. This can shorten the time from the start-up of the reactor to the start of the power transmission system, whereby the operation efficiency of the power plant can be improved. (Moriyama, K.)

  6. Permanent cessation of Tokai power plant's operation

    International Nuclear Information System (INIS)

    Satoh, T.

    1998-01-01

    Tokai power plant (166MWe, Magnox type: GCR) is the first commercial reactor in Japan and has been kept operating stable since its commissioning in July 1996. During this period it has produced electricity of approximately 27.7 billion KWh (as of March 1997) and its stable operation has contributed greatly to the stable supply of electricity in Japan. Furthermore, technologies in various fields have been developed, demonstrated and accumulated through the construction and operation of Tokai power plant. It also contributes to training for many nuclear engineers, and constructions and operations of nuclear power stations by other Japanese power companies. As a pioneer, it has been achieved to develop and popularize Japanese nuclear power generation. On the other hand, Tokai power plant has small capacity in its electric power output, even though the size of the reactor and heat exchangers are rather bigger than those of LWR due to the characteristics of GCR. Therefore, the generation cost is higher than the LWR. Since there is no plant whose reactor type is the same as that of Tokai power plant, the costs for maintenance and fuel cycle are relatively higher than that of LWR. Finally we concluded that the longer we operate it, the less we can take advantage of it economically. As a result of the evaluation for the future operation of Tokai power plant including the current status for supply of electricity by the Japanese utilities and study of decommissioning by Japanese government, we decided to have a plan of stopping its commercial operation of Tokai power plant in the end of March, 1998, when we completely consume its fuel that we possess. From now on, we set about performing necessary studies and researches on the field of plant characterization, remote-cutting, waste disposal for carrying out the decommissioning of Tokai power plant safely and economically. We are going to prepare the decommissioning planning for Tokai power plant in a few years based on the

  7. Operating experience with BWR nuclear power

    International Nuclear Information System (INIS)

    Bonsdorf, Magnus von.

    1986-01-01

    The two-unit nuclear power station in Olkiluoto on the western coast of Finland produces about 20 per cent of the electricity consumption of the country. The first unit, TVO-I was first connected to the national grid in September 1978 and TVO-II in February 1980. The original rated power output of each unit was 660 MWe, corresponding to the thermal power of 2000 MW from the reactor. Technical modifications allowed the power to be uprated by 8%. The operating statistics (load factors etc.) are given and the outage experience discussed. The radiological history shows very low radioactivity and dose levels have been maintained at the plant. (UK)

  8. Non-symmetric elliptic operators on bounded Lipschitz domains in the plane

    Directory of Open Access Journals (Sweden)

    David J. Rule

    2007-10-01

    Full Text Available We consider divergence form elliptic operators $L = mathop{ m div} A abla$ in $mathbb{R}^2$ with a coefficient matrix $A = A(x$ of bounded measurable functions independent of the $t$-direction. The aim of this note is to demonstrate how the proof of the main theorem in [4] can be modified to bounded Lipschitz domains. The original theorem states that the $L^p$ Neumann and regularity problems are solvable for $1 < p < p_0$ for some $p_0$ in domains of the form ${(x,t : phi(x < t}$, where $phi$ is a Lipschitz function. The exponent $p_0$ depends only on the ellipticity constants and the Lipschitz constant of $phi$. The principal modification of the argument for the original result is to prove the boundedness of the layer potentials on domains of the form ${X = (x,t : phi(mathbf{e}cdot X < mathbf{e}^perpcdot X }$, for a fixed unit vector $mathbf{e} = (e_1,e_2$ and $mathbf{e}^perp = (-e_2,e_1$. This is proved in [4] only in the case $mathbf{e} = (1,0$. A simple localisation argument then completes the proof.

  9. Institute of Nuclear Power Operations (INPO)

    International Nuclear Information System (INIS)

    Pack, R.W.

    1980-01-01

    The electric utility industry established the Institute of Nuclear Power Operations, or INPO, the purpose of which is to ensure the highest quality of operations in nuclear power plants. INPO will be an industry self-help instrument focusing on human factors. From top management to the operator trainee, it will measure utility performance against benchmarks of excellence and help utilities reach those benchmarks throughout training and operating programs. INPO will see that the utilities ferret out lessons for all from the abnormal operating experiences of any. It will do everything possible to assist utilities in meeting its certification requirements, but will have the clout to see that those requirements are met. INPO is also managing the nationwide system of utility emergency response capability

  10. Operator training simulator for nuclear power plant

    International Nuclear Information System (INIS)

    Shiozuka, Hiromi

    1977-01-01

    In nuclear power plants, training of the operators is important. In Japan, presently there are two training centers, one is BWR operation training center at Okuma-cho, Fukushima Prefecture, and another the nuclear power generation training center in Tsuruga City, Fukui Prefecture, where the operators of PWR nuclear power plants are trained. This report describes the BWR operation training center briefly. Operation of a nuclear power plant is divided into three stages of start-up, steady state operation, and shut down. Start-up is divided into the cold-state start-up after the shut down for prolonged period due to periodical inspection or others and the hot-state start-up from stand-by condition after the shut down for a short time. In the cold-state start-up, the correction of reactivity change and the heating-up control to avoid excessive thermal stress to the primary system components are important. The BWR operation training center offers the next three courses, namely beginner's course, retraining course and specific training course. The training period is 12 weeks and the number of trainees is eight/course in the beginner's course. The simulator was manufactured by modeling No. 3 plant of Fukushima First Nuclear Power Station, Tokyo Electric Power Co. The simulator is composed of the mimic central control panel and the digital computer. The software system comprises the monitor to supervise the whole program execution, the logic model simulating the plant interlock system and the dynamic model simulating the plant physical phenomena. (Wakatsuki, Y.)

  11. Licensing operators for commercial nuclear power plants

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1988-01-01

    The human element in the operation of commercial nuclear power plants is of utmost importance. Not only must the operators be technically competent in the execution of numerous complicated tasks, they must be capable of working together as a team to diagnose dynamic plant conditions to ensure that their plants are operated safely. The significance of human interaction skills and crew communications has been demonstrated most vividly in TMI and Chernobyl. It follows that the NRC must retain its high standards for licensing operators. This paper discusses activities and initiatives being employed by the NRC to enhance the reliability of its licensing examinations, and to build a highly qualified examiner work force

  12. Explicit Bounds and Sharp Results for the Composition Operators Preserving the Exponential Class

    Directory of Open Access Journals (Sweden)

    Fernando Farroni

    2016-01-01

    Full Text Available Let f:Ω⊂Rn→Rn be a quasiconformal mapping whose Jacobian is denoted by Jf and let EXP(Ω be the space of exponentially integrable functions on Ω. We give an explicit bound for the norm of the composition operator Tf: u∈EXP(Ω↦u∘f-1∈EXP(f(Ω and, as a related question, we study the behaviour of the norm of log⁡Jf in the exponential class. The A∞ property of Jf is the counterpart in higher dimensions of the area distortion formula due to Astala in the plane and it is the key tool to prove the sharpness of our results.

  13. Spectrum of the multigroup neutron transport operator for bounded spatial domains

    International Nuclear Information System (INIS)

    Larsen, E.W.

    1979-01-01

    The spectrum of the multigroup neutron transport operator A is studied for bounded spatial regions D which consist of a finite number of material subregions. Our main results provide simple conditions on the material cross sections which guarantee that (1) A possesses eigenvalues in the finite plane; (2) A possesses a ''leading'' eigenvalue lambda 0 which is real, not less than the real part of any other eigenvalue, and to which there corresponds at least one nonnegative eigenfunction psi/sub lambda/0; and (3) A possesses a ''dominant'' eigenvalue lambda 0 which is real, simple, greater than the real part of any other eigenvalue, and whose eigenfunction psi/sub lambda/0 satisfies psi/sub lambda/0> or =0 and ∫psi/sub lambda/0d 2 Ω>0. We give examples to illustrate the results and to show that a leading eigenvalue need not be simple, nor its eigenfunction(s) positive

  14. Entropic cohering power in quantum operations

    Science.gov (United States)

    Xi, Zhengjun; Hu, Ming-Liang; Li, Yongming; Fan, Heng

    2018-02-01

    Coherence is a basic feature of quantum systems and a common necessary condition for quantum correlations. It is also an important physical resource in quantum information processing. In this paper, using relative entropy, we consider a more general definition of the cohering power of quantum operations. First, we calculate the cohering power of unitary quantum operations and show that the amount of distributed coherence caused by non-unitary quantum operations cannot exceed the quantum-incoherent relative entropy between system of interest and its environment. We then find that the difference between the distributed coherence and the cohering power is larger than the quantum-incoherent relative entropy. As an application, we consider the distributed coherence caused by purification.

  15. An analyser for power plant operations

    International Nuclear Information System (INIS)

    Rogers, A.E.; Wulff, W.

    1990-01-01

    Safe and reliable operation of power plants is essential. Power plant operators need a forecast of what the plant will do when its current state is disturbed. The in-line plant analyser provides precisely this information at relatively low cost. The plant analyser scheme uses a mathematical model of the dynamic behaviour of the plant to establish a numerical simulation. Over a period of time, the simulation is calibrated with measurements from the particular plant in which it is used. The analyser then provides a reference against which to evaluate the plant's current behaviour. It can be used to alert the operator to any atypical excursions or combinations of readings that indicate malfunction or off-normal conditions that, as the Three Mile Island event suggests, are not easily recognised by operators. In a look-ahead mode, it can forecast the behaviour resulting from an intended change in settings or operating conditions. Then, when such changes are made, the plant's behaviour can be tracked against the forecast in order to assure that the plant is behaving as expected. It can be used to investigate malfunctions that have occurred and test possible adjustments in operating procedures. Finally, it can be used to consider how far from the limits of performance the elements of the plant are operating. Then by adjusting settings, the required power can be generated with as little stress as possible on the equipment. (6 figures) (Author)

  16. Power operation, measurement and methods of calculation of power distribution

    International Nuclear Information System (INIS)

    Lindahl, S.O.; Bernander, O.; Olsson, S.

    1982-01-01

    During the initial fuel loading of a BWR core, extensive checks and measurements of the fuel are performed. The measurements are designed to verify that the reactor can always be safely operated in compliance with the regulatory constraints. The power distribution within the reactor core is evaluated by means of instrumentation and elaborate computer calculations. The power distribution forms the basis for the evaluation of thermal limits. The behaviour of the reactor during the ordinary modes of operation as well as during transients shall be well understood and such that the integrity of the fuel and the reactor systems is always well preserved. (author)

  17. The sharp bounds on general sum-connectivity index of four operations on graphs

    Directory of Open Access Journals (Sweden)

    Shehnaz Akhter

    2016-09-01

    Full Text Available Abstract The general sum-connectivity index χ α ( G $\\chi_{\\alpha}(G$ , for a (molecular graph G, is defined as the sum of the weights ( d G ( a 1 + d G ( a 2 α $(d_{G}(a_{1}+d_{G}(a_{2}^{\\alpha}$ of all a 1 a 2 ∈ E ( G $a_{1}a_{2}\\in E(G$ , where d G ( a 1 $d_{G}(a_{1}$ (or d G ( a 2 $d_{G}(a_{2}$ denotes the degree of a vertex a 1 $a_{1}$ (or a 2 $a_{2}$ in the graph G; E ( G $E(G$ denotes the set of edges of G, and α is an arbitrary real number. Eliasi and Taeri (Discrete Appl. Math. 157:794-803, 2009 introduced four new operations based on the graphs S ( G $S(G$ , R ( G $R(G$ , Q ( G $Q(G$ , and T ( G $T(G$ , and they also computed the Wiener index of these graph operations in terms of W ( F ( G $W(F(G$ and W ( H $W(H$ , where F is one of the symbols S, R, Q, T. The aim of this paper is to obtain sharp bounds on the general sum-connectivity index of the four operations on graphs.

  18. Modifications at operating nuclear power plants

    International Nuclear Information System (INIS)

    Duffy, T.J.; Gazda, P.A.

    1985-01-01

    Modifications at operating nuclear power plants offer the structural engineer many challenges in the areas of scheduling of work, field adjustments, and engineering staff planning. The scheduling of structural modification work for operating nuclear power plants is normally closely tied to planned or unplanned outages of the plant. Coordination between the structural engineering effort, the operating plant staff, and the contractor who will be performing the modifications is essential to ensure that all work can be completed within the allotted time. Due to the inaccessibility of some areas in operating nuclear power plants or the short time available to perform the structural engineering in the case of an unscheduled outrage, field verification of a design is not always possible prior to initiating the construction of the modification. This requires the structural engineer to work closely with the contractor to promptly resolve problems due to unanticipated interferences or material procurement problems that may arise during the course of construction. The engineering staff planning for structural modifications at an operating nuclear power plant must be flexible enough to permit rapid response to the common ''fire drills,'' but controlled enough to ensure technically correct designs and to minimize the expenditure of man-hours and the resulting engineering cost

  19. Operating experience at Scottish Nuclear's power stations

    International Nuclear Information System (INIS)

    Blackburn, P.

    1991-01-01

    A brief history is presented of the design and operation of the four Scottish nuclear power stations currently run by Scottish Nuclear, namely Hunterston 'A' and 'B' and the Torness reactors. A design flaw in the Magnox reactor at Hunterston 'A' led to it being operated at lower than optimal temperature and hence producing less power. For Hunterston 'B' reactor the Advanced Gas Cooled design prototype was used. Operating setbacks and successes are noted. The design chosen for Torness embraced all the good points of Hunterston 'B' but sought to eliminate its faults. After 26 years of successful operation Hunterston 'A' is now being decommissioned, while the other three stations continue to generate electricity successfully. (UK)

  20. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-02-01

    During the third quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. The annual maintenance outages of the Loviisa plant units were held during the report period. All events during this quarter are classified as Level hero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were below authorised limits. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  1. Smart Shipboard Power System Operation and Management

    DEFF Research Database (Denmark)

    Kanellos, Fotis D.; Anvari-Moghaddam, Amjad; Guerrero, Josep M.

    2016-01-01

    as all-electric ships (AESs), the need for more cost-effective and emission-aware solutions is augmented. Such onboard systems are prone to sudden load variations due to the changing weather conditions as well as mission profile, thus they require effective power management systems (PMSs) to operate...... optimally under different working conditions. In this paper, coordinated optimal power management at the supply/demand side of a given AES is studied with regard to different objectives and related technical/environmental constraints. The optimal power management problem is formulated as a mixed...

  2. The operating staff of nuclear power plants

    International Nuclear Information System (INIS)

    Schlegel, G.; Christ, W.

    1988-01-01

    The training of its staff is one of the pillars of the safe and economical operation of a power plant. This is why power plant owners began to systematically train their staff already in the 50s, and why they created central training facilities. Staff members who have undergone this training make an indispensable contribution to the acceptedly high safety and availability of German power plants. The substantial cost of creating training facilities and of schooling plant staff is considered to be an investment for the future. Low labour turnover permits careful observation and development of staff and leads to a high standard of knowledge and experience. (orig./HSCH) [de

  3. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-09-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost all the time in the first quarter of 1992. The load factor average was 99.8%. All events which are classified on the International Nuclear Event Scale were level 0/below scale on the Scale. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure, originating from the nuclear power plants, were detected in samples collected in the vicinity of the nuclear power plants

  4. Atomic power plant and its operation method

    International Nuclear Information System (INIS)

    Yamamoto, Fumiaki; Higashio, Satoru.

    1986-01-01

    Purpose: To improve operation performance by partially restraining local over power in the axial power distribution of the reactor core by properly controlling the reactor pressure and furthermore by smoothly and properly performing reactor start-up operation in a short time while maintaining fuel integrity. Method: With the reactor pressure input to the pressure controller from the pressure detector, the valve opening of the main steam adjusting valve is adjusted so that the pressure will decrease when the reactor is started up. Also the adjusting valve is controlled so that the pressure will be lower than the set value of rated pressure, thus changing the axial distribution of void. In the meantime, with the stored state of xenon stored along with the increase of reactor power taken into consideration, the reactor pressure is increased as high as the rated value until the reactor power reaches to the rated power, thereby alleviating the local increase of reactor power without changing the whole reactor power and also enabling substantial reduction of reactor start-up time while maintaining reactor integrity. (Horiuchi, T.)

  5. Operating experience of Fugen Nuclear Power Station

    International Nuclear Information System (INIS)

    Ohteru, Shigeru; Kaneko, Jun; Kawahara, Toshio; Matsumoto, Mitsuo

    1987-01-01

    The prototype ATR 'Fugen' developed as one of the national project has verified the performance and reliability of the advanced thermal reactor system through the operation for about eight years since 1979, and the elucidation of the characteristics in plutonium utilization and the development and verification of the tuilizing techniques have been advanced. Besides, the operational results and the achievement of the technical development are successively reflected to the design of a demonstration reactor. In this paper, the outline of Fugan and the operational results are reported. The ATR Fugen Power Station is that of the prototype reactor of heavy water moderated, boiling light water cooled, pressure tube type, having the electric output of 165 MW. It started the full scale operation on March 20, 1979, and as of January, 1987, the total generated electric power reached about 7 billion kWh, the time of power generation was about 43,000 h, and the average capacity factor was 60.6 %. Plutonium utilization techniques, the flow characteristics and the dynamic plant characteristics of a pressure tube type reactor, the operational characteristics of a heavy water system and the techniques of handling heavy water containing tritium, and the operational reliability and maintainability of the machinery and equipment installed have been studied. (Kako, I.)

  6. 14 CFR 27.695 - Power boost and power-operated control system.

    Science.gov (United States)

    2010-01-01

    ... Systems § 27.695 Power boost and power-operated control system. (a) If a power boost or power-operated... failure of all engines. (b) Each alternate system may be a duplicate power portion or a manually operated... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Power boost and power-operated control...

  7. 14 CFR 29.695 - Power boost and power-operated control system.

    Science.gov (United States)

    2010-01-01

    ... Systems § 29.695 Power boost and power-operated control system. (a) If a power boost or power-operated... failure of all engines. (b) Each alternate system may be a duplicate power portion or a manually operated... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Power boost and power-operated control...

  8. Independent System Operators and Biomass Power

    International Nuclear Information System (INIS)

    Porter, Kevin L.

    1999-01-01

    Since the Federal Energy Regulatory Commission issued its landmark open access transmission rule in 1996, the idea of creating and establishing independent system operators (ISOs) has gained momentum. ISOs may help combine individual utility transmission systems into more regional transmission networks, which ultimately will allow biomass companies to transmit power over longer distances while paying a single transmission rate. To the extent that ISOs are combined or operated with power exchanges, however, biomass companies will likely face even more competitive market pressures. Few operators have experience with ISOs and power exchanges, but preliminary results show that short-term electricity market prices are probably too low for most biomass companies to compete against. Without policy measures, biomass companies may have to pursue strategic opportunities with short-term, spot-market sales; direct bilateral sales to customers; alternative power exchanges; and perhaps a ''green'' power market and sales to ancillary service markets. In addition, prices will likely be more volatile in a restructured market so biomass generators should be selling during those times

  9. Operating years 1993 through 1995 power purchases

    International Nuclear Information System (INIS)

    1991-12-01

    Bonneville Power Administration (BPA) is obligated to supply electric power to its contractual customers. Based on a forecast of growing customer loads and assuming Critical Period water conditions in the Columbia River Basin, BPA is planning to meet a firm energy deficit during the four operating years (OY) 1992 through 1995, i.e., August 1991 through July 1995. BPA has executed several power purchase agreements to cover the projected OY 1992 deficit. The proposed action is to extend two existing one-year power purchase agreements for an additional three years to cover the four-year Critical Period energy deficit. The extension of these two one-year power purchase agreements would: (1) increase BPA's firm energy load-carrying capability; (2) allow BPA to meet its firm energy contractual commitments over the remaining three years of the four-year Critical Period from August 1, 1992, to July 31, 1995; (3) provide flexibility for BPA's use of hydroelectric resources over the Critical Period; and (4) increase system reliability. Under Critical Period water conditions, absent the proposed action, projected loads would exceed the capability of the Federal power system to serve those loads. The purpose of BPA's proposed action is to assure consistency with its statutory responsibilities, including those found in the Pacific Northwest Electric Power Planning and Conservation Act (Northwest Power Act)

  10. Coherence-limited solar power conversion: the fundamental thermodynamic bounds and the consequences for solar rectennas

    Science.gov (United States)

    Mashaal, Heylal; Gordon, Jeffrey M.

    2014-10-01

    Solar rectifying antennas constitute a distinct solar power conversion paradigm where sunlight's spatial coherence is a basic constraining factor. In this presentation, we derive the fundamental thermodynamic limit for coherence-limited blackbody (principally solar) power conversion. Our results represent a natural extension of the eponymous Landsberg limit, originally derived for converters that are not constrained by the radiation's coherence, and are irradiated at maximum concentration (i.e., with a view factor of unity to the solar disk). We proceed by first expanding Landsberg's results to arbitrary solar view factor (i.e., arbitrary concentration and/or angular confinement), and then demonstrate how the results are modified when the converter can only process coherent radiation. The results are independent of the specific power conversion mechanism, and hence are valid for diffraction-limited as well as quantum converters (and not just classical heat engines or in the geometric optics regime). The derived upper bounds bode favorably for the potential of rectifying antennas as potentially high-efficiency solar converters.

  11. Regulatory framework for nuclear power plant operation

    International Nuclear Information System (INIS)

    Perez Alcaniz, T.; Esteban Barriendos, M.

    1995-01-01

    As the framework of standards and requirements covering each phase of nuclear power plant project and operation developed, plant owners defined their licensing commitments (codes, rules and design requirements) during the project and construction phase before start-up and incorporated regulatory requirements imposed by the regulatory Body during the licensing process prior to operation. This produces a regulatory framework for operating a plant. It includes the Licensing Basis, which is the starting point for analyzing and incorporating new requirements, and for re-evaluation of existing ones. This presentation focuses on the problems of applying this regulatory framework to new operating activities, in particular to new projects, analyzing new requirements, and reconsidering existing ones. Clearly establishing a plant's licensing basis allows all organizations involved in plant operation to apply the requirements in a more rational way. (Author)

  12. Operating experience in nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The nuclear power plants in the Federal Republic of Germany kept their portion of power supply into the public grid system constant in 1983, compared to 1982. The generation had an absolute increase of 3.6% and amounts now to 65.9 TWh. Particularly mentioned should be the generation of the Grafenrheinfeld Nuclear Power Plant which is holding the 'World Record' with 9.969 TWh. The availability of the plants was generally satisfactory, as far as long-term retrofit measures with long outage periods were not necessary, as it was the case in Brunsbuettel and Wuergassen. The planned retrofit phases have been completed in all power plants. As far as safety is concerned, there was no reason to recommended a change of the present fundamental planning- and operation aspects. (orig.) [de

  13. Bounds on the order of vanishing of eigenfunctions of Schroedinger operators

    International Nuclear Information System (INIS)

    Hoffmann-Ostenhof, M.; Hoffmann-Ostenhof, T.

    1990-01-01

    We study L 2 -solutions of (-Δ+V-E)ψ = 0 in R n , n ≥ 2 and derive a sharp upper bound to l x 0 (ψ) in terms of x 0 , E and V under rather restrictive assumptions on V. We show for V smooth that an upper bound to l x 0 (ψ) implies an upper bound to the dimension of the eigenspace associated to E. 16 refs. (Authors)

  14. Decontamination of operational nuclear power plants

    International Nuclear Information System (INIS)

    1981-06-01

    In order to reduce the radiation fields around nuclear power plants, and, consequently, to limit the radiation exposure of and dose commitments to the operating and maintenance personnel, the contamination build-up should be kept to a minimum. The most fruitful approach, from the point of view of economics and efficiency, is to tackle the problems of contamination and decontamination in the design and construction phases of the reactor. To do this, knowledge gained from the operation of existing power reactors should be used to make improvements in new designs. New structural materials with low corrosion rates or whose constituents are not activated by neutrons should also be used. For older reactors, in most cases it is already too late to incorporate design changes without extensive and expensive modifications. For these plants, decontamination remains the most efficient way to reduce radiation fields. The aim of this report is to deal with the different decontamination methods that may be applied to nuclear power plant circuits and equipment during operation. The factors that have to be considered in determining the type and the extent of the methods used are the engineering and the planning of the decontamination operation and the treatment of the resulting waste generated during the process are also discussed

  15. Wind power plant in grid operation

    International Nuclear Information System (INIS)

    Heier, S.

    1993-01-01

    There are new prospects for electrical energy supply in coastal regions and on islands if one succeeds in integrating the available wind energy, dependent on the weather, into existing and to be developed supply structures. Apart from the supply of energy, effects on the grid and on the electrical consumer are gaining in importance. For wind power plants, the operating behaviour is appreciably determined by the electro-technical concept. The mechanical/electrical energy conversion with the corresponding grid connection and plant control play an important part here. Results of measurements and computer simulation make the differences in the behaviour of wind power plants clear. (orig.) [de

  16. Operating experience from Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The total production of electricity from Swedish nuclear power plants was 70.5 TWh during 1998, which is the second highest yearly production ever. Production losses due to low demand totaled 5.1 TWh combined for all twelve units and production losses due to coastdown operation totaled an additional 0.5 TWh. The reason for this low power demand was a very good supply of water to the hydropower system. Hydroelectric power production was 73.6 TWh, an increase by roughly 5 TWh since 1997. Hence, the hydroelectric power production substantially exceeded the 64 TWh expected during a normal year, i.e. a year with average rainfall. Remaining production sources, mainly fossil fuel electricity production combined with district heating, contributed with 10 TWh. The total electricity production was 154.2 TWh, the highest yearly production ever. The total electricity consumption including transmission losses was 143.5 TWh. This is also the highest consumption ever and an increase by one percent compared to 1997. The preliminary net result of the electric power trade shows a net export by 10.7 TWh. The figures above are calculated from the preliminary production results. A comprehensive report on electric power supply and consumption in Sweden is given in the 1998 Annual Report from the Swedish Power Association. Besides Oskarshamn 1, all plants have periodically been operated in load-following mode, mostly because of the abundant supply of hydropower. The energy availability for the three boiling water reactors at Forsmark averaged 93.3 % and for the three pressure water reactors at Ringhals 91.0 %, both figures are the highest ever noted. In the section `Special Reports` three events of importance to safety that occurred during 1998 are reported. The events were all rated as level 1 according to the International Nuclear Event Scale (INES) Figs, tabs.; Also available in Swedish

  17. Operating experience from Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1999-01-01

    The total production of electricity from Swedish nuclear power plants was 70.5 TWh during 1998, which is the second highest yearly production ever. Production losses due to low demand totaled 5.1 TWh combined for all twelve units and production losses due to coastdown operation totaled an additional 0.5 TWh. The reason for this low power demand was a very good supply of water to the hydropower system. Hydroelectric power production was 73.6 TWh, an increase by roughly 5 TWh since 1997. Hence, the hydroelectric power production substantially exceeded the 64 TWh expected during a normal year, i.e. a year with average rainfall. Remaining production sources, mainly fossil fuel electricity production combined with district heating, contributed with 10 TWh. The total electricity production was 154.2 TWh, the highest yearly production ever. The total electricity consumption including transmission losses was 143.5 TWh. This is also the highest consumption ever and an increase by one percent compared to 1997. The preliminary net result of the electric power trade shows a net export by 10.7 TWh. The figures above are calculated from the preliminary production results. A comprehensive report on electric power supply and consumption in Sweden is given in the 1998 Annual Report from the Swedish Power Association. Besides Oskarshamn 1, all plants have periodically been operated in load-following mode, mostly because of the abundant supply of hydropower. The energy availability for the three boiling water reactors at Forsmark averaged 93.3 % and for the three pressure water reactors at Ringhals 91.0 %, both figures are the highest ever noted. In the section 'Special Reports' three events of importance to safety that occurred during 1998 are reported. The events were all rated as level 1 according to the International Nuclear Event Scale (INES)

  18. Dynamic bounds for power and efficiency of non-ideal energy converters under nonlinear transfer laws

    International Nuclear Information System (INIS)

    Sieniutycz, Stanislaw

    2009-01-01

    We present a thermodynamic approach to simulation and modeling of nonlinear energy converters, in particular radiation engines. Novel results are obtained especially for dynamical engines when the temperature of the propelling medium decreases in time due to a continual decrease of the medium's internal energy caused by the power production. Basic thermodynamic principles determine the converter's efficiency and work limits in terms of the entropy production. The real work is a cumulative effect obtained in a system of a resource fluid, a sequence of engines, and an infinite bath. Nonlinear modeling involves dynamic optimization in which the classical expression for efficiency at maximum power is generalized to endoirreversible machines and nonlinear transfer laws. The primary result is a finite-rate generalization of the classical, reversible work potential (exergy). The generalized work function depends on thermal coordinates and a dissipation index, h, i.e. a Hamiltonian of the minimum entropy production problem. This generalized work function implies stronger bounds on work delivered or supplied than the reversible work potential. The role of the nonlinear analyses and dynamic optimization is shown especially for radiation engines. As an example of the kinetic work limit, generalized exergy of radiation fluid is estimated in terms of finite rates, quantified by the Hamiltonian h

  19. Statistical operation of nuclear power plants

    International Nuclear Information System (INIS)

    Gauzit, Maurice; Wilmart, Yves

    1976-01-01

    A comparison of the statistical operating results of nuclear power stations as issued in the literature shows that the values given for availability and the load factor often differ considerably from each other. This may be due to different definitions given to these terms or even to a poor translation from one language into another. A critical analysis of these terms as well as the choice of a parameter from which it is possible to have a quantitative idea of the actual quality of the operation obtained is proposed. The second section gives, on an homogenous basis and from the results supplied by 83 nuclear power stations now in operation, a statistical analysis of their operating results: in particular, the two light water lines, during 1975, as well as the evolution in terms of age, of the units or the starting conditions of the units during their first two operating years. Test values thus obtained are compared also to those taken 'a priori' as hypothesis in some economic studies [fr

  20. Training device for nuclear power plant operators

    International Nuclear Information System (INIS)

    Schoessow, G. J.

    1985-01-01

    A simulated nuclear energy power plant system with visible internal working components comprising a reactor adapted to contain a liquid with heating elements submerged in the liquid and capable of heating the liquid to an elevated temperature, a steam generator containing water and a heat exchanger means to receive the liquid at an elevated temperature, transform the water to steam, and return the spent liquid to the reactor; a steam turbine receiving high energy steam to drive the turbine and discharging low energy steam to a condenser where the low energy steam is condensed to water which is returned to the steam generator; an electric generator driven by the turbine; indicating means to identify the physical status of the reactor and its contents; and manual and automatic controls to selectively establish normal or abnormal operating conditions in the reactor, steam generator, pressurizer, turbine, electric generator, condenser, and pumps; and to be selectively adjusted to bring the reactor to acceptable operating condition after being placed in an abnormal operation. This device is particularly useful as an education device in demonstrating nuclear reactor operations and in training operating personnel for nuclear reactor systems and also as a device for conducting research on various safety systems to improve the safety of nuclear power plants

  1. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, Pekka

    1987-07-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. No event in the report period, or in the whole year of 1986, essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. For remedying certain defects found in the adminstrative procedures concerning plant operation and maintenance, the Loviisa power plant was shut down for several days in September

  2. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, Pekka

    1987-05-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the perssonnel or the environment. For remedying certain defects found in the administrative procedures concerning plant operation and maintenance, the Loviisa power plant was shut down for several days

  3. Determining the bounds of skilful forecast range for probabilistic prediction of system-wide wind power generation

    Directory of Open Access Journals (Sweden)

    Dirk Cannon

    2017-06-01

    Full Text Available State-of-the-art wind power forecasts beyond a few hours ahead rely on global numerical weather prediction models to forecast the future large-scale atmospheric state. Often they provide initial and boundary conditions for nested high resolution simulations. In this paper, both upper and lower bounds on forecast range are identified within which global ensemble forecasts provide skilful information for system-wide wind power applications. An upper bound on forecast range is associated with the limit of predictability, beyond which forecasts have no more skill than predictions based on climatological statistics. A lower bound is defined at the lead time beyond which the resolved uncertainty associated with estimating the future large-scale atmospheric state is larger than the unresolved uncertainty associated with estimating the system-wide wind power response to a given large-scale state.The bounds of skilful ensemble forecast range are quantified for three leading global forecast systems. The power system of Great Britain (GB is used as an example because independent verifying data is available from National Grid. The upper bound defined by forecasts of GB-total wind power generation at a specific point in time is found to be 6–8 days. The lower bound is found to be 1.4–2.4 days. Both bounds depend on the global forecast system and vary seasonally. In addition, forecasts of the probability of an extreme power ramp event were found to possess a shorter limit of predictability (4.5–5.5 days. The upper bound on this forecast range can only be extended by improving the global forecast system (outside the control of most users or by changing the metric used in the probability forecast. Improved downscaling and microscale modelling of the wind farm response may act to decrease the lower bound. The potential gain from such improvements have diminishing returns beyond the short-range (out to around 2 days.

  4. Tokamak power reactor ignition and time dependent fractional power operation

    International Nuclear Information System (INIS)

    Vold, E.L.; Mau, T.K.; Conn, R.W.

    1986-06-01

    A flexible time-dependent and zero-dimensional plasma burn code with radial profiles was developed and employed to study the fractional power operation and the thermal burn control options for an INTOR-sized tokamak reactor. The code includes alpha thermalization and a time-dependent transport loss which can be represented by any one of several currently popular scaling laws for energy confinement time. Ignition parameters were found to vary widely in density-temperature (n-T) space for the range of scaling laws examined. Critical ignition issues were found to include the extent of confinement time degradation by alpha heating, the ratio of ion to electron transport power loss, and effect of auxiliary heating on confinement. Feedback control of the auxiliary power and ion fuel sources are shown to provide thermal stability near the ignition curve

  5. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-06-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  6. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-03-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  7. Mobile Hybrid Power System Theory of Operation

    OpenAIRE

    Pierce, Timothy M. Jr.

    2016-01-01

    Efficiency is a driving constraint for electrical power systems as global energy demands are ever increasing. Followed by the introduction of diesel generators, electricity has become available in more locations than ever. However, operating a diesel generator on its own is not the most energy efficient. This is because the high crest factor loads, of many applications, decrease the fuel efficiency of a hydrocarbon generator. To understand this, we need to understand how an electrical load af...

  8. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-09-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear safety and radiation protection which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing modifications at the nuclear power plants and issues relating to the use of nuclear energy which are of general interest are also reported. The reports include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the first quarter of 1993, a primary feedwater system pipe break occurred at Loviisa 2, in a section of piping after a feedwater pump. The break was erosion-corrosion induced. Repairs and inspections interrupted power generation for seven days. On the International Nuclear Event Scale the event is classified as a level 2 incident. Other events in the first quarter of 1993 had no bearing on nuclear safety and radiation protection

  9. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-05-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole fourth quarter of 1991. The load factor average was 94.7 % (the whole year 90.9 %). All the events in the last annual quarter, which are classified on the International Nuclear Event Scale, were below scale/level 0. Also the events which occurred in the other quarters of the year 1991 were rated at the scale's lowest levels. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure originating in nuclear power plants were detected in the samples collected in the vicinity of the nuclear power plants

  10. Safety goals for nuclear power plant operation

    International Nuclear Information System (INIS)

    1983-05-01

    This report presents and discusses the Nuclear Regulatory Commission's, Policy Statement on Safety Goals for the Operation of Nuclear Power Plants. The safety goals have been formulated in terms of qualitative goals and quantitative design objectives. The qualitative goals state that the risk to any individual member of the public from nuclear power plant operation should not be a significant contributor to that individual's risk of accidental death or injury and that the societal risks should be comparable to or less than those of viable competing technologies. The quantitative design objectives state that the average risks to individual and the societal risks of nuclear power plant operation should not exceed 0.1% of certain other risks to which members of the US population are exposed. A subsidiary quantitative design objective is established for the frequency of large-scale core melt. The significance of the goals and objectives, their bases and rationale, and the plan to evaluate the goals are provided. In addition, public comments on the 1982 proposed policy statement and responses to a series of questions that accompanied the 1982 statement are summarized

  11. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-08-01

    In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  12. The Federal Administrative Court confirms unlawfulness of nuclear power moratorium. Political primacy is only valid in the bounds of justice

    International Nuclear Information System (INIS)

    Leidinger, Tobias

    2014-01-01

    With its decision on December 20 th , the Federal Administrative Court (BVwerfG) came to the legally valid conclusion that after the Fukushima nuclear power plant accident, the supervision court order related to the law on nuclear installation by the Hessian Ministry for the Environment, in order to stop operating nuclear power plants Biblis A and B for 3 months or rather not to put in operation again, was unlawful (BVwerfG 7 B 18.13 und 7 B 19.13). Beforehand, the Hessian Administrative Court (Hess. VGH) had already pronounced its judgement on February 27 th 2013. The supervising orders were part of the so-called nuclear power moratorium. They were issued after the resolution of the federal government, at demand of the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) towards their nearby countries, and were identically executed by the supervisory authority of the other site-countries. Besides Biblis in Hesse, nuclear power plants in Neckarwestheim I and Philippsburg 1, Baden-Wurttemberg, Isar 1 in Bavaria, Unterweser in Lower Saxony, as well as Brunsbuettel in Schleswig-Holstein, were affected. However only RWE took legal action and was now affirmed - after the Hessian VGH verdict- by the highest German administrative court: The nuclear power moratorium - the first step to withdrawal of nuclear power in Germany - was unlawful. The decision taken by the BVerwG - as well as the one by the Hessian VGH - indicates a juridical clear and precise argumentation. The partially polemic and unobjective critic, which the VHG-verdict experienced, did not disguise, just as little as the political conflict concerning the withdrawal from nuclear energy, the view of federal judges, regarding the decision-relevant questions nor did they influence their reply. The political primacy finds its limits in the bounds of justice. Existing rights do not become thus a paper waste because there is a fundamental decision. This takes effectiveness for

  13. The armenian power system operation stability investigation accounting putting new power systems into operation

    International Nuclear Information System (INIS)

    Yeghiazaryan, L.V.; Hakobyan, S.G.; Gharibyan, G.V.; Harutyunyan, G.S.; Galstyan, G.H.

    2010-01-01

    The description of the power systems operation stability failure caused by the system significant emergency states occurred during the last working period in Armenian and USA power systems is performed. With the use of PSSTME-31 software portfolio of Siemens Firm a design model is developed and transient electromechanical process calculations for Armenian power system are performed. The accuracy of the model is checked by comparing real-time transient state parameters and their reproduction calculation results.The Armenia - Iran current power transmission lines permissible limit under the condition of the static and dynamic stability requirements and in case of the new thermal power units maintenance are defined

  14. Innovation of nuclear power operation in KHNP

    International Nuclear Information System (INIS)

    Lee, Byung Sik

    2007-01-01

    KHNP has operated the nuclear plants with two major functional areas, operation and maintenance very similar to fossil plant operation. KHNP has recently sent engineers to high performing nuclear power plants in usa and canada for training and familiarization with the engineering organization operation, processes and programs. KHNP has also established a system engineering section at each plant since July 2003. However the system engineering section has not achieved desired results because of a lack of understanding to implement the engineering function and processes. This indicates poor change management preparedness and implementation at KHNP. In September 2005. K SET/(KHNP Special Engineering Task Force Team) was established to enhance KHNP's engineering capability: especially the System Engineering function. The team consists of 13 members: 9 KHNP engineers (including one team manager) who have more than one year's experience working or training in USA or Canada, and 4 foreign engineers who have a wide range of experience and knowledge of engineering areas in Nuclear Power Plants of USA. The team first performed a gap analysis comparing performance and work behavior of 2 nd plant to those of world best practice. this was done by interviewing employees and reviewing relevant document. The team identified 26 significant performance gaps among 120 function areas, prioritized the 26 gape, and verified the effectiveness of the selection of gaps by comparing it to SNPM(standard nuclear performance model) developed by NEI

  15. Human factors in nuclear power plant operation

    International Nuclear Information System (INIS)

    Sabri, Z.A.; Husseiny, A.A.

    1980-01-01

    An extensive effort is being devoted to developing a comprehensive human factor program that encompasses establishment of a data base for human error prediction using past operation experience in commercial nuclear power plants. Some of the main results of such an effort are reported including data retrieval and classification systems which have been developed to assist in estimation of operator error rates. Also, statistical methods are developed to relate operator error data to reactor type, age, and specific technical design features. Results reported in this paper are based on an analysis of LER's covering a six-year period for LWR's. Developments presently include a computer data management program, statistical model, and detailed error taxonomy

  16. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-12-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO 1 and II were in operation for almost the whole second quarter of 1991. The load factor average was 87.4 %. In consequence of a fire, which broke out in the switchgear building, connections to both external grids were lost and TVO II relied on power supplied by four back-up diesels for 7.5 hrs. The event is classified as Level 2 on the International Nuclear Event Scale. The process of examining the non-leaking fuel bundles removed from the Loviisa nuclear reactors has continued. The examinations have revealed, so far, that the uppermost spacing lattices of the bundles exhibit deformations similar to those detected in the leaking fuel bundles removed from the reactors. This event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale) on the Scale. The Finnish Centre for Radiation and Nuclear Safety has assessed the safety of the Loviisa and Olkiluoto nuclear power plants based on the new regulations issued on 14.2.1991 by the Council of State. The safety regulations are much more stringent than those in force when the Loviisa and Olkiluoto nuclear power plants were built. The assessment indicated that the TVO nuclear power plant meets these safety regulations. The Loviisa nuclear power plant meets the requirements with the exception of certain requirements related to the ensuring of safety functions and provision for accidents. At the Loviisa nuclear power plant there are several projects under consideration to enhance safety

  17. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-03-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole third quarter of 1991. Longer interruptions in electricity generation were caused by the annual maintenances of the Loviisa plant units. The load factor average was 81.7 %. In a test conducted during the annual maintenance outage of Loviisa 1 it was detected that the check valve of the discharge line of one pressurized emergency make-up tank did not open sufficiently at the tank's hydrostatic pressure. In connection with a 1988 modification, a too tightly dimensioned bearing had been mounted on the valve's axle rod and the valve had not been duly tested after the operation. The event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale). Occupational radiation doses and releases of radioactive material off-site were below authorised limits in this quarter. Only small amounts of radioactive materials originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  18. Academic training for nuclear power plant operators

    International Nuclear Information System (INIS)

    Jones, D.W.

    1982-01-01

    In view of the increasing emphasis being placed upon academic training of nuclear power plant operators, it is important that institutions of higher education develop and implement programs which will meet the educational needs of operational personnel in the nuclear industry. Two primary objectives must be satisfied by these programs if they are to be effective in meeting the needs of the industry. One objective is for academic quality. The other primary objective is for programs to address the specialized needs of the nuclear plant operator and to be relevant to the operator's job. The Center for Nuclear Studies at Memphis State University, therefore, has developed a total program for these objectives, which delivers the programs, and/or appropriate parts thereto, at ten nuclear plant sites and with other plants in the planning stage. The Center for Nuclear Studies program leads to a Bachelor of Professional Studies degree in nuclear industrial operations, which is offered through the university college of Memphis State University

  19. Power-law versus log-law in wall-bounded turbulence: A large-eddy simulation perspective

    KAUST Repository

    Cheng, W.; Samtaney, Ravi

    2014-01-01

    The debate whether the mean streamwise velocity in wall-bounded turbulent flows obeys a log-law or a power-law scaling originated over two decades ago, and continues to ferment in recent years. As experiments and direct numerical simulation can

  20. Smart Shipboard Power System Operation and Management

    Directory of Open Access Journals (Sweden)

    Fotis D. Kanellos

    2016-11-01

    Full Text Available During recent years, optimal electrification of isolated offshore systems has become increasingly important and received extensive attention from the maritime industry. Especially with the introduction of electric propulsion, which has led to a total electrification of shipboard power systems known as all-electric ships (AESs, the need for more cost-effective and emission-aware solutions is augmented. Such onboard systems are prone to sudden load variations due to the changing weather conditions as well as mission profile, thus they require effective power management systems (PMSs to operate optimally under different working conditions. In this paper, coordinated optimal power management at the supply/demand side of a given AES is studied with regard to different objectives and related technical/environmental constraints. The optimal power management problem is formulated as a mixed-integer nonlinear programming (MINLP model and is solved using a metaheuristic algorithm. To show the effectiveness and applicability of the proposed PMS, several test scenarios are implemented and related simulation results are analyzed and compared to those from conventional methods.

  1. Operation control device for nuclear power plants

    International Nuclear Information System (INIS)

    Suto, Osamu.

    1982-01-01

    Purpose: To render the controlling functions of a central control console more centralized by constituting the operation controls for a nuclear power plant with computer systems having substantially independent functions such as those of plant monitor controls, reactor monitor management and CRT display and decreasing interactions between each of the systems. Constitution: An input/output device for the input of process data for a nuclear power plant and indication data for a plant control console is connected to a plant supervisory and control computer system and a display computer system, the plant supervisory control computer system and a reactor and management computer system are connected with a CRT display control device, a printer and a CRT display input/output device, and the display computer system is connected with the CRT display control device and the CRT display unit on the central control console, whereby process input can be processed and displayed at high speed. (Yoshino, Y.)

  2. Regional Power Authority urged for TMI operations

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    If the Three Mile Island (TMI) unit 1 returns to service, state ownership with a Regional Power Authority to oversee its operation and complete the cleanup of unit 2 would benefit ratepayers and avoid lengthy lawsuits, according to an Arthur Young and Company report to the New Jersey Board of Utilities. The report rejects continued ownership by General Public Utilities (GPU), merger, divestiture, and other options. It also outlines several conditions necessary for a Regional Power Authority: adequate rate relief, restart of TMI-1, congressional tax exemption, and approval by the GPU board and stockholders. The report recommends that Jersey Central divest itself of GPU to avoid financial disaster if GPU should declare bankruptcy, but it advises maintaining the flexibility to exercise long-term options

  3. Power System Operations With Water Constraints

    Science.gov (United States)

    Qiu, F.; Wang, J.

    2015-12-01

    The interdependency between water and energy, although known for many decades, has not received enough attention until recent events under extreme weather conditions (especially droughts). On one hand, water and several types of energy supplies have become increasingly scarce; the demand on water and energy continues to grow. On the other hand, the climate change has become more and more disruptive (i.e., intensity and frequency of extreme events), causing severe challenges to both systems simultaneously. Water and energy systems have become deeply coupled and challenges from extreme weather events must be addressed in a coordinated way across the two systems.In this work, we will build quantitative models to capture the interactions between water and energy systems. We will incorporate water constraints in power system operations and study the impact of water scarcity on power system resilience.

  4. Training of nuclear power plant operating personnel

    International Nuclear Information System (INIS)

    Anon.

    1980-04-01

    A collection is presented containing 11 papers submitted at a conference on the selection and education of specialists for operation and maintenance of nuclear power plants. The conference was attended by specialists from universities and colleges, research institutes and production plants. It debated the methods and aims of both general and specialized theoretical and practical personnel education, the proposals for teaching centre equipment, the use of simulators, computers and other aids in the teaching process; training on school reactors was included. A proposal was put forward of the system of education, the teaching process itself, the content of the basic theoretical subjects, and the method of testing pupils' knowledge. The importance was stressed of establishing a national coordination centre to safeguard the syllabus, methodology, teaching aids, and also the training proper. The system of personnel education in the Paks nuclear power plant, Hungary, is presented as an example. (M.S.)

  5. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1990-03-01

    In the Quarterly Reports on the operation of the Finnish nuclear power plants such incidents and observations are described relating to nuclear and radiation safety which the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, considers safety-related. During the third quarter of 1989 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 39.0% of the total Finnish electricity production in this quarter. The load factor average of the nuclear power plant units was 78.9%. At Loviisa 1, two holes were found in the feedwater distributor of one steam generator. Corresponding wall thinning corrosion was also detected in the walls of two other distributors. The holes were found on the feedwater distributor upper surface in the joint of the secondary circuit feedwater pipe. One hole was about 20 mm x 50 mm in size and the other was a pit hole ca 5 mm in diameter. Metal power had entered the primary circuit at TVO I. This was observed during a post-scram plant start-up. Several control rod drive units had become jammed so tight that control rod withdrawal failed. Metal powder did not hamper reactor scram under the prevailing circumstances because the drive units are prone to jamming only after a control rod is almost fully inserted and because the forces which insert a control rod by various means (electrical, hydraulic) are 6-8 fold compared with the withdrawing force

  6. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, P.

    1986-08-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. (author)

  7. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Ottosson, C.

    1989-05-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  8. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Haenninen, R.; Koponen, H.; Nevander, O.; Paltemaa, R.; Poellaenen, I.; Rannila, P.; Valtonen, K.; Vilkamo, O.

    1988-02-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  9. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Heimburger, H.

    1988-08-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  10. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.

    1985-09-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as significant. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and capacity factors of the plants. (author)

  11. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.; Lehtinen, P.

    1985-11-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as significant. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and load factors of the plants. (author)

  12. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Haenninen, R.

    1988-09-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hzard to the personnel or the environment

  13. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    1988-04-01

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tubulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  14. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.

    1985-01-01

    This general review of the operation of the Finnish nuclear power plants in the second quarter of the year 1984 concentrates on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as significant. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and availability of the plants. (author)

  15. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.

    1985-05-01

    This general review of the operation of the Finnish nuclear power plants in the third quarter of the year 1984 concentrates on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as significant. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and capacity factors of the plants. (author)

  16. Performance management for nuclear power plant operators

    International Nuclear Information System (INIS)

    Fan Pengfei

    2014-01-01

    Fuel was loaded to Unit 3 of the second power plant in May 2010. The Second Operation Division stepped in the operation stage from production preparation and commissioning and exploration of performance management was started. By means of performance evaluation, a closed loop of performance management was formed, staff enthusiasm improved, and potential capability inspired through evaluation, analysis and improvement. The performance evaluation covers attitude, skill, efficiency, performance, teamwork sense, cooperation, etc. Quantitative appraisal was carried out through 31 objective indicators of the working process and results. According to the evaluation results and personal interviews, indicators were modified. Through the performance evaluation, positive guidance is provided to the employees to promote the development of employees, departments and the enterprise. (authors)

  17. Operating health analysis of electric power systems

    Science.gov (United States)

    Fotuhi-Firuzabad, Mahmud

    The required level of operating reserve to be maintained by an electric power system can be determined using both deterministic and probabilistic techniques. Despite the obvious disadvantages of deterministic approaches there is still considerable reluctance to apply probabilistic techniques due to the difficulty of interpreting a single numerical risk index and the lack of sufficient information provided by a single index. A practical way to overcome difficulties is to embed deterministic considerations in the probabilistic indices in order to monitor the system well-being. The system well-being can be designated as healthy, marginal and at risk. The concept of system well-being is examined and extended in this thesis to cover the overall area of operating reserve assessment. Operating reserve evaluation involves the two distinctly different aspects of unit commitment and the dispatch of the committed units. Unit commitment health analysis involves the determination of which unit should be committed to satisfy the operating criteria. The concepts developed for unit commitment health, margin and risk are extended in this thesis to evaluate the response well-being of a generating system. A procedure is presented to determine the optimum dispatch of the committed units to satisfy the response criteria. The impact on the response wellbeing being of variations in the margin time, required regulating margin and load forecast uncertainty are illustrated. The effects on the response well-being of rapid start units, interruptible loads and postponable outages are also illustrated. System well-being is, in general, greatly improved by interconnection with other power systems. The well-being concepts are extended to evaluate the spinning reserve requirements in interconnected systems. The interconnected system unit commitment problem is decomposed into two subproblems in which unit scheduling is performed in each isolated system followed by interconnected system evaluation

  18. Development and application of nuclear power operation database

    International Nuclear Information System (INIS)

    Shao Juying; Fang Zhaoxia

    1996-01-01

    The article describes the development of the Nuclear Power Operation Database which include Domestic and Overseas Nuclear Event Scale Database, Overseas Nuclear Power Operation Abnormal Event Database, Overseas Nuclear Power Operation General Reliability Database and Qinshan Nuclear Power Operation Abnormal Event Database. The development includes data collection and analysis, database construction and code design, database management system selection. The application of the database to provide support to the safety analysis of the NPPs which have been in commercial operation is also introduced

  19. Power operated contact apparatus for superconductive circuit

    Energy Technology Data Exchange (ETDEWEB)

    Woods, D.C.; Efferson, K.R.

    1989-10-10

    This patent describes a power operated contact apparatus for extending and retracting one or more electrical leads into and out of a cryostat for making and breaking, at a cryogenic temperature, electrical contact with a superconductive circuit. It comprises at least one rigid elongated lead for extending into a cold space of the cryostat which is at or near a cryogenic temperature. The lead having an inner end and a outer end; a connector fixed at the inner end of the lead for making electrical contact in the cold space with a connector of the superconductive circuit; guide means journaling the lead for allowing the lead to move axially relative to the guide means and sealing against the lead; a foundation for sealed attachment to the cryostat and to the guide means so that the connector on the inner end of the lead is extendable into making electrical contact with the connector of the superconductive circuit in the cold space; power operated means mounted on the foundation and fixed to the outer end of the lead for extending and retracting the lead to and from making electrical contact with the superconductive circuit in the cold space; and means for de-icing the exterior of the leads and guide means when the leads are connected to the superconducting circuit.

  20. Operation of Power Grids with High Penetration of Wind Power

    Science.gov (United States)

    Al-Awami, Ali Taleb

    The integration of wind power into the power grid poses many challenges due to its highly uncertain nature. This dissertation involves two main components related to the operation of power grids with high penetration of wind energy: wind-thermal stochastic dispatch and wind-thermal coordinated bidding in short-term electricity markets. In the first part, a stochastic dispatch (SD) algorithm is proposed that takes into account the stochastic nature of the wind power output. The uncertainty associated with wind power output given the forecast is characterized using conditional probability density functions (CPDF). Several functions are examined to characterize wind uncertainty including Beta, Weibull, Extreme Value, Generalized Extreme Value, and Mixed Gaussian distributions. The unique characteristics of the Mixed Gaussian distribution are then utilized to facilitate the speed of convergence of the SD algorithm. A case study is carried out to evaluate the effectiveness of the proposed algorithm. Then, the SD algorithm is extended to simultaneously optimize the system operating costs and emissions. A modified multi-objective particle swarm optimization algorithm is suggested to identify the Pareto-optimal solutions defined by the two conflicting objectives. A sensitivity analysis is carried out to study the effect of changing load level and imbalance cost factors on the Pareto front. In the second part of this dissertation, coordinated trading of wind and thermal energy is proposed to mitigate risks due to those uncertainties. The problem of wind-thermal coordinated trading is formulated as a mixed-integer stochastic linear program. The objective is to obtain the optimal tradeoff bidding strategy that maximizes the total expected profits while controlling trading risks. For risk control, a weighted term of the conditional value at risk (CVaR) is included in the objective function. The CVaR aims to maximize the expected profits of the least profitable scenarios, thus

  1. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1990-12-01

    During the second quarter of 1990 the Finnish nuclear plant units Loviisa 1 and 2 and TVO and II were in commercial operation for most of the time. The feedwater pipe rupture at Loviisa 1 and the resulting inspections and repairs at both Loviisa plant units brought about an outage the overall duration of which was 32 days. The annual maintenance outages of the TVO plant units were arranged during the report period and their combined duration was 31.5 days. Nuclear electricity accounted for 35.3% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 83.0%. Three events occurred during the report period which are classified as Level 1 on the International Nuclear Event Scale: feedwater pipe rupture at Loviisa 1, control rod withdrawal at TVO I in a test during an outage when the hydraulic scram system was rendered inoperable and erroneous fuel bundle transfers during control rod drives maintenance at TVO II. Other events during this quarter are classified as Level Zero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. Only small amounts of nuclides originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  2. Interactive videodisc training for power plant operations

    International Nuclear Information System (INIS)

    Nolan, R.; Nolan, J.; Campos, M.; Haukom, R.; Quentin, G.

    1990-01-01

    During the last several years, professionals in the personal computer and video fields have seen their two technologies coming together. This merging has created a new medium called multimedia. Multimedia provides the user with the interactivity of the personal computer and the realism of live-action television. It appears to be a perfect marriage for education, training and selling applications. As multimedia productions continue to be produced and tested with high marks, business and industry are becoming interested. The Interactive Videodisc Trainer (IVT) is a demonstration of how multimedia technology can be used by the electric power industry for operator training. Although the subject for this pilot program is the Claus sulfur recovery unit at the Cool Water Integrated Gasification Combined Cycle plant, similar courseware can be put to use for training at any type of power plant. The goal is to show many of the features and capabilities inherent in this powerful new training tool, so that utilities can begin to see how it could work for them

  3. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1990-08-01

    During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

  4. Operation guide device for nuclear power plants

    International Nuclear Information System (INIS)

    Araki, Tsuneyasu

    1982-01-01

    Purpose: To enable to maintain the soundness of nuclear fuels and each of equipments by compensating the effect of the xenon density on the reactor core thermal power resulted upon load following operation of a nuclear reactor. Constitution: The device comprises an instrumentation system for measuring the status of the nuclear reactor, a reactor core performance calculator for calculating the reactor core performance based on the output from the instrumentation system, a xenon density calculator for calculating the xenon density based on the output from the performance calculator, a memory unit for storing the output from the reactor core performance calculator and the xenon density calculator and for transferring the stored memory to a nuclear reactor status forecasting device and an alternative load pattern searching device for searching, in cooperation with the memory unit, an alternative load pattern which is within an operation restrictive condition and most closed to a demanded load pattern when a monitor for the deviation from the flowrate distribution detects the deviation from the operation restrictive conditions. (Yoshino, Y.)

  5. Power generation operations management : due diligence

    International Nuclear Information System (INIS)

    Hill, D.; Paul, G.

    1998-01-01

    The practical applications of an emergency planning process within Edmonton Power's power generation operations management were discussed. A project was initiated to develop a corporate emergency planning standard which incorporates existing emergency procedures into a unified management system. The need for an emergency planning standard which would establish planning criteria became evident after a tornado hit Edmonton on July 31, 1987, killing 27 and causing $330 million in damages. The emergency plans in effect at the time were less than adequate. The components of the new emergency planning standards include: (1) policy and hazard analysis, (2) functional responsibilities, (3) initial response, (4) emergency support, (5) mutual aid, (6) business protection and recovery, (7) emergency response debriefing, (8) training and exercises, and (9) emergency plan distribution and maintenance. A brief summary of the intent of each section, and some of the experiences learned during the development of this emergency plan are described for the benefit of those who may be called upon to develop an integrated emergency plan in the future. 1 ref

  6. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-12-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations related to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing plant modifications and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and their load factors are also given. At the Loviisa 1 plant unit one of two specially-backed AC busbars was lost during the second quarter of 1993. A ca. 30 minute voltage break caused malfunctions in the plant unit's electrical equipment and rendered inoperable certain components important to safety. The event is rated on the International Nuclear Event Scale (INES) at level 1. In inspections carried out at TVO II during the annual maintenance outage, the number of cracks detected in control rod structural material was higher than usual. When cracks occur, part of boron carbide, the power regulating medium in control rods, may wash into the reactor water and control rod shutdown capability may be impaired. The event is rated on the INES at level 1. Other events in the second quarter of 1993 had no bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

  7. Method to operate power reactors with light water cooling

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.

    1976-01-01

    The invention provides a possibility to 'condition' the fuel of a power plant used in base load operation, i.e. to bring it to such a high power density level that the local excesses arising with the occasional total power changes, remain below the power densities reached in normal operation (conditioning level). (orig./RW) [de

  8. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-12-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well TVO I and II were in operation for almost the whole second quarter of 1992. Longer breaks in production were caused by the annual maintenance of the TVO plant units. The load factor was 87.4 %. At TVO I it was detected during the annual maintenance outage when removing nuclear fuel assemblies from the reactor that one assembly had been loaded into the reactor in an incorrect manner during the previous year's annual maintenance: the assembly was slightly higher than the other assemblies. The water cooling the nuclear fuel partly by-passed the fuel assembly and the coolant flow proper passing through the assembly was below design. The fuel assembly's cooling had been sufficient during the whole operating cycle but could have essentially deteriorated during certain transients with the danger of consequent damage to some fuel rods. On the International Nuclear Event Scale the event is classified as level 1. Other events in this quarter which are classified on the International Nuclear Event Scale were level 0/below scale on the scale

  9. Containment and Consensus-based Distributed Coordination Control for Voltage Bound and Reactive Power Sharing in AC Microgrid

    DEFF Research Database (Denmark)

    Han, Renke; Meng, Lexuan; Ferrari-Trecate, Giancarlo

    2017-01-01

    This paper offers a highly flexible and reliable control strategy to achieve voltage bounded regulation and accurate reactive power sharing coordinately in AC Micro-Grids. A containment and consensus-based distributed coordination controller is proposed, by which each output voltage magnitude can...... be bounded within a reasonable range and the accurate reactive power sharing among distributed generators can be also achieved. Combined with the two proposed controllers and electrical part of the AC Micro-Grid, a small signal model is fully developed to analyze the sensitivity of different control...... parameters. The effectiveness of the proposed controller in case of load variation, communication failure, plug-and-play capability are verified by the experimental setup as an islanded Micro-Grid....

  10. Operating modes and practical power flow analysis of bidirectional isolated power interface for distributed power systems

    International Nuclear Information System (INIS)

    Wen, Huiqing; Su, Bin

    2016-01-01

    Highlights: • Four operating modes of Dual-Phase-Shift control for Dual Active Bridge converter are presented. • Effects of “minor parameters” such as the deadtime and power device voltage drops are analyzed. • Accurate power flow models with Dual-Phase-Shift control are developed and verified with experimental results. • Optimal operating mode is determined with respect to the efficiency improvement. • Measured efficiency of the Dual Active Bridge converter is improved up to 14%. - Abstract: Due to the intermittent nature of the renewable energy sources including photovoltaic and wind energy, the energy storage systems are essential to stabilize dc bus voltage. Considering the discharge depth of super-capacitors and energy-storage batteries, the bidirectional isolated power interface will operate for a wide range of voltage and power. This study focuses on in-depth analysis of the dual-active-bridge dc–dc converter that is controlled by the dual-phase-shift scheme to improve the conversion efficiency in distributed power system. The power flow of each operating mode with dual-phase-shift control is characterized based on a detailed analysis of the effects of “minor parameters”, including the deadtime and power device voltage drops. The complete output power plane of the dual-active-bridge converter with dual-phase-shift control is obtained and compared with experimental results. The optimal operating mode is determined according to the practical output power range and the power flow characteristics. Experimental evaluation shows the effectiveness of the proposed power flow model with dual-phase-shift control and significant efficiency improvement using the optimal mode of dual-phase-shift compared with the conventional phase shift control.

  11. Change-management. From commercial power operation to post power operation and decommissioning

    International Nuclear Information System (INIS)

    Wasinger, Karl

    2015-01-01

    Transition from power generation to decommissioning challenges utilities. Power generation is mainly characterized by a stable working environment and constant workload, decommissioning and dismantling, however, by transformation and change. Also, changing requirements for the workforce's skills challenge the organization and its senior management. Ensuring effective and efficient performance, while maintaining motivation of staff, requires adjustment of management processes as well as of operational organization and human resources management. AREVA has more than 20 years of experience in decommissioning of own nuclear fuel cycle plants in France, as well as of other large plants and power reactors in Germany, the United Kingdom and the US. Therefore, the group has developed and successfully implemented integrated change management processes. The implementation of well-established and proven methods, developed by the productive industry and adjusted to the nuclear regulatory requirements, significantly improves the performance and efficiency of means and methods in use. The AREVA Performance Improvement Process defines concrete approaches to identify and improve potential deficits of productivity in six main areas (decommissioning scenarios and stra-tegies, waste treatment and logistics, operations management, supply chain, regulatory monitoring and controls as well as dismantling operation). Nuclear plant and facility owners around the world benefit from AREVA experts well experienced in execution of large and complex decommissioning projects.

  12. Supervision functions - Secure operation of sustainable power systems

    DEFF Research Database (Denmark)

    Morais, Hugo; Zhang, Xinxin; Lind, Morten

    2013-01-01

    of power systems operation control. The use of PMUs allows more penetration of DG mainly, with technologies based on renewable resources with intermittent and unpredictable operation such a wind power. This paper introduces the Secure Operation of Sustainable Power Systems (SOSPO) project. The SOSPO...... project tries to respond to the question "How to ensure a secure operation of the future power system where the operating point is heavily is fluctuating?" focusing in the Supervision module architecture and in the power system operation states. The main goal of Supervision module is to determine...... the power system operation state based on new stability and security parameters derived from PMUs measurement and coordinate the use of automatic and manual control actions. The coordination of the control action is based not only in the static indicators but also in the performance evaluation of control...

  13. Design and development of high voltage high power operational ...

    Indian Academy of Sciences (India)

    Applications of power operational amplifiers (opamps) are increasing day by day in the industry as they are used in audio amplifiers, Piezo transducer systems and the electron deflection systems. Power operational amplifiers have all the features of a general purpose opamp except the additional power handling capability.

  14. Generalized Robin Boundary Conditions, Robin-to-Dirichlet Maps, and Krein-Type Resolvent Formulas for Schr\\"odinger Operators on Bounded Lipschitz Domains

    OpenAIRE

    Gesztesy, Fritz; Mitrea, Marius

    2008-01-01

    We study generalized Robin boundary conditions, Robin-to-Dirichlet maps, and Krein-type resolvent formulas for Schr\\"odinger operators on bounded Lipschitz domains in $\\bbR^n$, $n\\ge 2$. We also discuss the case of bounded $C^{1,r}$-domains, $(1/2)

  15. Computing Confidence Bounds for Power and Sample Size of the General Linear Univariate Model

    OpenAIRE

    Taylor, Douglas J.; Muller, Keith E.

    1995-01-01

    The power of a test, the probability of rejecting the null hypothesis in favor of an alternative, may be computed using estimates of one or more distributional parameters. Statisticians frequently fix mean values and calculate power or sample size using a variance estimate from an existing study. Hence computed power becomes a random variable for a fixed sample size. Likewise, the sample size necessary to achieve a fixed power varies randomly. Standard statistical practice requires reporting ...

  16. Guide for training nuclear power plant operators

    International Nuclear Information System (INIS)

    Cox, J.A.; Cagle, C.D.; Corbett, B.L.; Culbert, W.H.; Hamrick, T.P.; Hurt, S.S.; McCord, R.V.; Poteet, K.H.; Bates, A.E.G.; Casto, W.R.

    1977-01-01

    Topics covered include basic preparation, radiation safety and control, principles of reactor operation, general operating characteristics, facility design, safety systems, instrumentation, reactor theory, fuel handling and core parameters, radioactive material handling, and administrative procedures

  17. Virginia Power's nuclear operations: Leading by example

    International Nuclear Information System (INIS)

    Kuehn, S.E.

    1995-01-01

    Success has been a long time coming for Virginia Power's nuclear units, but after a record run and some of the shortest refueling outages ever, the rest of the industry could learn a few things. This article describes the changes made by Virginia Power at its Surry and North Anna plants. Virginia Power's recipe for success called for equal amounts of individual initiative, management savvy, engineering discipline, organization, dedication, perseverance, pride, introspection, motivation, and humility

  18. Preparation and practice for nuclear power plant operation

    International Nuclear Information System (INIS)

    Wu Xuesong; Lu Tiezhong

    2015-01-01

    The operational preparation of the nuclear power plant is an important work in nuclear power plant production preparation. Due to the construction period of nuclear power plant from starting construction to production is as long as five years, the professional requirements of nuclear power operation are very strict, and the requirements for nuclear safety are also extremely high. Especially after the Fukushima accident, higher requirements for the safe operation of nuclear power plant are posed by competent authorities of the national level, regulatory authorities and each nuclear power groups. Based on the characteristics of the construction phase of nuclear power plant and in combination with engineering practice, this paper expounds the system established in the field of nuclear power plant operation and generally analyses the related management innovation. (authors)

  19. Role of check operators in achieving operational excellence at Virginia Power's nuclear stations

    International Nuclear Information System (INIS)

    Shriver, B.L.; Williams, T.M.; Stewart, W.L.

    1987-01-01

    Virginia Power has implemented a Check Operator Program as a part of its commitment to excellence in the operation of the North Anna and Surry nuclear power stations. The Check Operator Program utilizes highly qualified licensed personnel to independently evaluate the performance of licensed operators and senior operators during normal, abnormal and simulated emergency conditions. Emphasis is placed upon individual and team performance as well as the procedures and training which support the operators. The check operators report to line management to ensure that their recommendations are implemented into the overall operations philosophy of the power station

  20. 33 CFR 209.141 - Coordination of hydroelectric power operations with power marketing agencies.

    Science.gov (United States)

    2010-07-01

    ... Commanders will develop, in coordination with their respective power marketing agency, a system for exchanging operating information. The system will include general operating information and information on... power operations with power marketing agencies. 209.141 Section 209.141 Navigation and Navigable Waters...

  1. The human factor in the operation of nuclear powered submarines

    International Nuclear Information System (INIS)

    Dambier, M.

    1982-05-01

    The conditions characterizing the operation of nuclear powered submarines are described and the precautionary measures suitable to reduce the incidence of human errors and their consequences are explained

  2. 47 CFR 73.664 - Determining operating power.

    Science.gov (United States)

    2010-10-01

    ... BROADCAST SERVICES Television Broadcast Stations § 73.664 Determining operating power. (a) The operating... substantially zero reactance and a resistance equal to the transmission line characteristic impedance. During...

  3. Improving operator quality at Genkai Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kuwano, Takeshi.

    1989-01-01

    Improvement in operator quality, or improvement in an operator's skill and professional knowledge, is of prime importance because of its great influence on safe and steady plant operation. This paper describes the education and training of reactor operators at the Genkai pressurized water reactor nuclear power plant with respect to the following topics: organization of Genkai power plant; education and training program management; training at the Nuclear Training Center; training and education on-site including emergency procedures training, normal operating procedures training, informational study of emergency conditions in existing plants, and all-around training of operators; qualifying tests for supervisors; and operator motivation

  4. Numerical Solution of Time-Dependent Problems with a Fractional-Power Elliptic Operator

    Science.gov (United States)

    Vabishchevich, P. N.

    2018-03-01

    A time-dependent problem in a bounded domain for a fractional diffusion equation is considered. The first-order evolution equation involves a fractional-power second-order elliptic operator with Robin boundary conditions. A finite-element spatial approximation with an additive approximation of the operator of the problem is used. The time approximation is based on a vector scheme. The transition to a new time level is ensured by solving a sequence of standard elliptic boundary value problems. Numerical results obtained for a two-dimensional model problem are presented.

  5. Determination of the self-adjoint matrix Schrödinger operators without the bound state data

    Science.gov (United States)

    Xu, Xiao-Chuan; Yang, Chuan-Fu

    2018-06-01

    (i) For the matrix Schrödinger operator on the half line, it is shown that the scattering data, which consists of the scattering matrix and the bound state data, uniquely determines the potential and the boundary condition. It is also shown that only the scattering matrix uniquely determines the self-adjoint potential and the boundary condition if either the potential exponentially decreases fast enough or the potential is known a priori on (), where a is an any fixed positive number. (ii) For the matrix Schrödinger operator on the full line, it is shown that the left (or right) reflection coefficient uniquely determine the self-adjoint potential if either the potential exponentially decreases fast enough or the potential is known a priori on (or ()), where b is an any fixed number.

  6. Operating experience with nuclear power plants 2015. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2016-07-01

    The VGB Technical Committee ''Nuclear Plant Operation'' has been exchanging operating experience about nuclear power plants for more than 30 years. Plant operators from several European countries are participating in the exchange. A report is given on the operating results achieved in 2015, events important to plant safety, special and relevant repair, and retrofit measures from Germany. The second part of this report will focus on nuclear power plant in Belgium, Finland, the Netherlands, Switzerland, and Spain.

  7. Human factors in nuclear power plant operations

    International Nuclear Information System (INIS)

    Swain, A.D.

    1980-08-01

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants

  8. Analysis of Upper Bound Power Output for a Wrist-Worn Rotational Energy Harvester from Real-World Measured Inputs

    International Nuclear Information System (INIS)

    Xue, T; Roundy, S; Ma, X; Rahn, C

    2014-01-01

    Energy harvesting from human motion addresses the growing need for battery-free health and wellness sensors in wearable applications. The major obstacles to harvesting energy in such applications are low and random frequencies due to the nature of human motion. This paper presents a generalized rotational harvester model in 3 dimensions to determine the upper bound of power output from real world measured data. Simulation results indicate much space for improvement on power generation comparing to existing devices. We have developed a rotational energy harvester for human motion that attempts to close the gap between theoretical possibility and demonstrated devices. Like previous work, it makes use of magnetically plucked piezoelectric beams. However, it more fully utilizes the space available and has many degrees of freedom available for optimization. Finally we present a prototype harvester based on the coupled harvester model with preliminary experimental validation

  9. Operator psychological selection system for nuclear power plant

    International Nuclear Information System (INIS)

    He Xuhong; Huang Xiangrui

    2004-01-01

    Based on a detailed job analysis of nuclear power plant operator including operation procedures analysis, interview with personnel familiar with operator job, and 9 events happened in the past in the plant involved operator error analysis, several operator work characteristics and performance influence factors are obtained. According to these specific characteristics and factors, referring to the psychological selection research results in the other related critical occupational fields, a full psychological selection system of nuclear power plant operator is forwarded in this paper, including 21 dimensions in 3 facets as general psychological ability, personality and psychological healthy. Practical measurement methods for the proposed selection dimensions are discussed in the end

  10. Power electronics basics operating principles, design, formulas, and applications

    CERN Document Server

    Rozanov, Yuriy; Chaplygin, Evgeny; Voronin, Pavel

    2015-01-01

    Power Electronics Basics: Operating Principles, Design, Formulas, and Applications provides fundamental knowledge for the analysis and design of modern power electronic devices. This concise and user-friendly resource:Explains the basic concepts and most important terms of power electronicsDescribes the power assemblies, control, and passive components of semiconductor power switchesCovers the control of power electronic devices, from mathematical modeling to the analysis of the electrical processesAddresses pulse-width modulation, power quality control, and multilevel, modular, and multicell

  11. China’s Nuclear Power Plants in Operation

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Qinshan Plant Phase I Located in Haiyan,Zhejiang Province,Qinshan Nuclear Power Plant Phase I is t he first 300-megawatt pressurized water reactor (PWR) nuclear power plant independently designed,constructed,operated and managed by China.The plant came into commercial operation in April 1994.

  12. Research on psychological evaluation method for nuclear power plant operators

    International Nuclear Information System (INIS)

    Fang Xiang; He Xuhong; Zhao Bingquan

    2007-01-01

    The qualitative and quantitative psychology evaluation methods to the nuclear power plant operators were analyzed and discussed in the paper. The comparison analysis to the scope and result of application was carried out between method of outline figure fitted and method of fuzzy synthetic evaluation. The research results can be referenced to the evaluation of nuclear power plant operators. (authors)

  13. Operating experience feedback on lose of offsite power supply for nuclear power plant

    International Nuclear Information System (INIS)

    Jiao Feng; Hou Qinmai; Che Shuwei

    2013-01-01

    The function of the service power system of a nuclear power plant is to provide safe and reliable power supply for the nuclear power plant facilities. The safety of nuclear power plant power supply is essential for nuclear safety. The serious accident of Fukushima Daiichi nuclear power plant occurred due to loss of service power and the ultimate heat sink. The service power system has two independent offsite power supplies as working power and auxiliary power. This article collected events of loss of offsite power supply in operating nuclear power plants at home and abroad, and analyzed the plant status and cause of loss of offsite power supply events, and proposed improvement measures for dealing with loss of offsite power supply. (authors)

  14. Structuring Economic Power for Stability Operations

    National Research Council Canada - National Science Library

    Wallen, Andrew T

    2006-01-01

    .... By their nature, these operations have a strong economic context. This thesis provides a methodology for evaluating current institutional structures and economic doctrines being forged among various government agencies...

  15. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose.

  16. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    International Nuclear Information System (INIS)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose

  17. Operation and maintenance of nuclear power plant

    International Nuclear Information System (INIS)

    1990-04-01

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

  18. Computing an operating parameter of a unified power flow controller

    Science.gov (United States)

    Wilson, David G.; Robinett, III, Rush D.

    2017-12-26

    A Unified Power Flow Controller described herein comprises a sensor that outputs at least one sensed condition, a processor that receives the at least one sensed condition, a memory that comprises control logic that is executable by the processor; and power electronics that comprise power storage, wherein the processor causes the power electronics to selectively cause the power storage to act as one of a power generator or a load based at least in part upon the at least one sensed condition output by the sensor and the control logic, and wherein at least one operating parameter of the power electronics is designed to facilitate maximal transmittal of electrical power generated at a variable power generation system to a grid system while meeting power constraints set forth by the electrical power grid.

  19. Computing an operating parameter of a unified power flow controller

    Science.gov (United States)

    Wilson, David G; Robinett, III, Rush D

    2015-01-06

    A Unified Power Flow Controller described herein comprises a sensor that outputs at least one sensed condition, a processor that receives the at least one sensed condition, a memory that comprises control logic that is executable by the processor; and power electronics that comprise power storage, wherein the processor causes the power electronics to selectively cause the power storage to act as one of a power generator or a load based at least in part upon the at least one sensed condition output by the sensor and the control logic, and wherein at least one operating parameter of the power electronics is designed to facilitate maximal transmittal of electrical power generated at a variable power generation system to a grid system while meeting power constraints set forth by the electrical power grid.

  20. Decomposing Objectives and Functions in Power System Operation and Control

    DEFF Research Database (Denmark)

    Heussen, Kai; Lind, Morten

    2009-01-01

    mix of challenges posed by renewable energy sources, demand response technologies and smartgrid concepts, affecting all areas of power system operation. Both, new control modes and changes in market design are required. This paper presents a mean-ends perspective to the analysis of the control......The introduction of many new energy solutions requires the adaptation of classical operation paradigms in power systems. In the standard paradigm, a power system is some equivalent of a synchronous generators, a power line and an uncontrollable load. This paradigm has been challenged by a diverse...... structures and operation paradigms in present power systems. In a top-down approach, traditional frequency- and area-control mechanisms are formalized. It is demonstrated that future power system operation paradigms with different generation control modes and controllable demand can be modeled in a coherent...

  1. Operation Modeling of Power Systems Integrated with Large-Scale New Energy Power Sources

    Directory of Open Access Journals (Sweden)

    Hui Li

    2016-10-01

    Full Text Available In the most current methods of probabilistic power system production simulation, the output characteristics of new energy power generation (NEPG has not been comprehensively considered. In this paper, the power output characteristics of wind power generation and photovoltaic power generation are firstly analyzed based on statistical methods according to their historical operating data. Then the characteristic indexes and the filtering principle of the NEPG historical output scenarios are introduced with the confidence level, and the calculation model of NEPG’s credible capacity is proposed. Based on this, taking the minimum production costs or the best energy-saving and emission-reduction effect as the optimization objective, the power system operation model with large-scale integration of new energy power generation (NEPG is established considering the power balance, the electricity balance and the peak balance. Besides, the constraints of the operating characteristics of different power generation types, the maintenance schedule, the load reservation, the emergency reservation, the water abandonment and the transmitting capacity between different areas are also considered. With the proposed power system operation model, the operation simulations are carried out based on the actual Northwest power grid of China, which resolves the new energy power accommodations considering different system operating conditions. The simulation results well verify the validity of the proposed power system operation model in the accommodation analysis for the power system which is penetrated with large scale NEPG.

  2. Computational Efficiency of Economic MPC for Power Systems Operation

    DEFF Research Database (Denmark)

    Standardi, Laura; Poulsen, Niels Kjølstad; Jørgensen, John Bagterp

    2013-01-01

    In this work, we propose an Economic Model Predictive Control (MPC) strategy to operate power systems that consist of independent power units. The controller balances the power supply and demand, minimizing production costs. The control problem is formulated as a linear program that is solved...

  3. Plant operational states analysis in low power and shutdown PSA

    International Nuclear Information System (INIS)

    He Jiandong; Qiu Yongping; Zhang Qinfang; An Hongzhen; Li Maolin

    2013-01-01

    The purpose of Plant Operational States (POS) analysis is to disperse the continuous and dynamic process of low power and shutdown operation, which is the basis of developing event tree models for accident sequence analysis. According to the design of a 300 MW Nuclear Power Plant Project, operating experience and procedures of the reference plant, a detailed POS analysis is carried out based on relative criteria. Then, several kinds of POS are obtained, and the duration of each POS is calculated according to the operation records of the reference plant. The POS analysis is an important element in low power and shutdown PSA. The methodology and contents provide reference for POS analysis. (authors)

  4. Anomalous dimension of subleading-power N-jet operators

    Science.gov (United States)

    Beneke, Martin; Garny, Mathias; Szafron, Robert; Wang, Jian

    2018-03-01

    We begin a systematic investigation of the anomalous dimension of subleading power N-jet operators in view of resummation of logarithmically enhanced terms in partonic cross sections beyond leading power. We provide an explicit result at the one-loop order for fermion-number two N-jet operators at the second order in the power expansion parameter of soft-collinear effective theory.

  5. Quality assurance during operation of nuclear power plants

    International Nuclear Information System (INIS)

    1994-01-01

    The general requirements applicable to the quality assurance of the Finnish nuclear power plants are presented in the Council of State Decision (395/91) and in the guide YVL 1.4. This guide specifies the quality assurance requirements to be applied during the operation of the nuclear power plants as well as of the other nuclear facilities. Quality assurance applies to all the activities and organizations with a bearing on the safe operation of the nuclear power plants. (5 refs.)

  6. Training and qualification of nuclear power plant operators (4)

    International Nuclear Information System (INIS)

    Ohsuga, Y.

    2009-01-01

    Training center using the simulators, instructor training, training upgrade, deployment of digital control panel and review of training were described with overseas practice. Recently, nuclear power plant on-site simulators were also used for respective operator training. Operator teamwork training, training team performance upgrade, reflection of operating experiences in nuclear power plant accidents, development of training support equipments and management of training records were needed to review and upgrade training and qualification programs. (T. Tanaka)

  7. Economics of satellite solar power system operation

    Energy Technology Data Exchange (ETDEWEB)

    Collins, P.Q.; Tomkins, R.

    1981-01-01

    The potential value of the Satellite Power System (SPS) concept depends partly on the effects of integrating SPS power into a national supply grid. Some of these effects are evaluated. The factors that would affect utilities appraisal of the system are briefly reviewed. The cost implications of these factors are considered under the headings Load factors, Reliability, System Planning and Integration, and Rectenna Siting and Transmission, with particular reference to the UK and W Europe. A method is proposed for studying the ground segment of the system; a utility could calculate the value it would place on microwave 'fuel' supplied by the space segment, thereby providing firm cost targets for this part of the system. 21 refs.

  8. Surveillance dosimetry of operating power plants

    International Nuclear Information System (INIS)

    McElroy, W.N.; Davis, A.I.; Gold, R.

    1981-01-01

    The main focus of the research efforts presently underway is the LWR power reactor surveillance program in which metallurgical test specimens of the reactor PV and dosimetry sensors are placed in three or more surveillance capsules at or near the reactor PV inner wall. They are then irradiated in a temperature and neutron flux-spectrum environment as similar as possible to the PV itself for periods of about 1.5 to 15 effective full-power years (EFPY), with removal of the last capsule at a fluence corresponding to the 30- to 40-year plant end-of-life (EOL) fluence. Because the neutron flux level at the surveillance position is greater than at the vessel, the test is accelerated wit respect to the vessel exposure, allowing early assessment of EOL conditions

  9. Vertex operators, semiclassical limit for soliton S-matrices and the number of bound states in Affine Toda Field Theories

    International Nuclear Information System (INIS)

    Kneipp, Marco A.C.

    1999-10-01

    Soliton time delays and the semiclassical limit for soliton S-matrices are calculated for non-simply laced Affine Toda Field Theories. The phase shift is written as a sum over bilinears on the soliton conserved charges. The results apply to any two solitons of any Affine Toda Field Theory. As a by-product, a general expression for the number of bound states and the values of the coupling in which the S-matrix can be diagonal are obtained. In order to arrive at these results, a vertex operator is constructed, in the principal gradation, for non-simply laced affine Lie algebras, extending the previous constructions for simply laced and twisted affine Lie algebras. (author)

  10. Uranium-isotope enrichment: application bounds of the separative power and separation work concepts

    Energy Technology Data Exchange (ETDEWEB)

    Novelli, P.

    1981-05-01

    The aim of this paper is a critical re-examination of the concepts of separative power, separation work and value function in order to understand if their extension to the new enrichment processes such as Laser Isotope Separation is possible.

  11. Preparing nuclear power plant units for operation

    International Nuclear Information System (INIS)

    Hudcovic, R.; Telgarsky, K.; Kmosena, J.

    1984-01-01

    The factors are listed which have to be taken into consideration for planning the unit operation, i.e., the implementation of planned repairs, checks of equipment and refuellings. All basic input data were evaluated as the basic for drawing up the schedule of routine repairs and overhauls for the coming period. (E.S.)

  12. Method of operating nuclear power plant

    International Nuclear Information System (INIS)

    Kodama, Tasuku.

    1991-01-01

    The present invention concerns a method of operating a plant in which the inside of a reactor container is filled with inert gases. That is, the pressure at the inside of the pressure vessel is controlled based on the values sent from an absolute pressure gage and a pressure low gage during usual operation. A pressure high alarm and a pressure high scram signal are generated from a pressure high detector and a scram pressure detector. With such a constitution, since the pressure at the inside of the reactor is always kept at a slightly positive level relative to the surrounding atmospheric pressure even when high atmospheric pressure approaches to the plant site, air does not flow into the reactor container. Accordingly, the oxygen concentration is not increased. When a low atmospheric pressure approaches, the control operation for the pressure at the inside of the container is not necessary. The amount of the inert gases consumed and the amount of radioactive materials released to the atmosphere are decreased. The method of the present invention improves the safety and the reliability of the reactor operation. (N.H.)

  13. Tianwan nuclear power plant operation and management practices

    International Nuclear Information System (INIS)

    Gu Yingbing

    2010-01-01

    Tianwan Nuclear Power Station is a high-tech cooperation project in nuclear sector in the spirit of promoting the political relationship, economic trading and international strategic partnership between China and Russia. It was listed as one of the key nuclear projects to be constructed during the 'Ninth Five-Year' Plan. In this article the author summarizes and feedbacks the practices of operation management in Tianwan Nuclear Power Station in 7 aspects of safety culture construction, operation team building, daily operation management, operation document management, plant chemistry control and management, solid, liquid and gaseous waste management and control of operation performance indicators. (author)

  14. Institute of nuclear power operations perspectives on PSA applications

    International Nuclear Information System (INIS)

    Webster, W.E.; Miller, W.J. Jr.

    1996-01-01

    The investment to develop a PSA is very substantial, and therefore, there is motivation to recover this investment through further use of the techniques used to develop it. It is not surprising that nuclear power plant staff are beginning to use PSA to make operational decisions. The Institute of Nuclear Power Operations is interested in those factors that impact the conduct of plant operations and therefore is actively monitoring the increased usage of PSA techniques. The purpose of this paper is to provide some thoughts and perspectives on the use of PSA as a factor in operational decision making, including decision making in activities performed by engineering, maintenance and operation personnel. (author)

  15. Computing and cognition in future power-plant operations

    International Nuclear Information System (INIS)

    Kisner, R.A.; Sheridan, T.B.

    1983-01-01

    The intent of this paper is to speculate on the nature of future interactions between people and computers in the operation of power plants. In particular, the authors offer a taxonomy for examining the differing functions of operators in interacting with the plant and its computers, and the differing functions of the computers in interacting with the plant and its operators

  16. Computing and cognition in future power plant operations

    International Nuclear Information System (INIS)

    Kisner, R.A.; Sheridan, T.B.

    1983-01-01

    The intent of this paper is to speculate on the nature of future interactions between people and computers in the operation of power plants. In particular, the authors offer a taxonomy for examining the differing functions of operators in interacting with the plant and its computers, and the differing functions of the computers in interacting with the plant and its operators

  17. Operating experience from Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    During 1997 the PWRs in Ringhals performed extremely well (capability factors 85-90%), the unit Ringhals 2 reached the best capability factor since commercial operation started in 1976. The BWRs made an average 76% capability, which is somewhat less than in 1996. The slightly reduced capability derives from ongoing modernization projects at several units. At the youngest plants, Forsmark 3 and Oskarshamn 3, capability and utilization were very high. Events and data for 1997 are given for each reactor, together with operational statistics for the years 1990-1997. A number of safety-related events are reported, which occurred st the Swedish plants during 1997. These events are classified as level 1 or higher on the international nuclear event scale (INES).

  18. Operating experience from Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1998-01-01

    During 1997 the PWRs in Ringhals performed extremely well (capability factors 85-90%), the unit Ringhals 2 reached the best capability factor since commercial operation started in 1976. The BWRs made an average 76% capability, which is somewhat less than in 1996. The slightly reduced capability derives from ongoing modernization projects at several units. At the youngest plants, Forsmark 3 and Oskarshamn 3, capability and utilization were very high. Events and data for 1997 are given for each reactor, together with operational statistics for the years 1990-1997. A number of safety-related events are reported, which occurred st the Swedish plants during 1997. These events are classified as level 1 or higher on the international nuclear event scale (INES)

  19. Feller-buncher Operator Breaks Power Line

    Science.gov (United States)

    J. Thompson

    2014-01-01

    On a summer day in the South, a rubber-tired feller-buncher operator was performing a first thinning in a pine plantation. The feller-buncher was working in a new area of the stand, removing the take-down row and thinning the two rows on either side. The trees were approximately 15 years old, and there was a relatively thick layer of underbrush. The stand of timber...

  20. Maximum power operation of interacting molecular motors

    DEFF Research Database (Denmark)

    Golubeva, Natalia; Imparato, Alberto

    2013-01-01

    , as compared to the non-interacting system, in a wide range of biologically compatible scenarios. We furthermore consider the case where the motor-motor interaction directly affects the internal chemical cycle and investigate the effect on the system dynamics and thermodynamics.......We study the mechanical and thermodynamic properties of different traffic models for kinesin which are relevant in biological and experimental contexts. We find that motor-motor interactions play a fundamental role by enhancing the thermodynamic efficiency at maximum power of the motors...

  1. Annual report on nuclear power station operational management, 1984

    International Nuclear Information System (INIS)

    1985-09-01

    As of the end of fiscal year 1984, 28 nuclear power plants were in operation in Japan, the total power output of which was 20.56 million kW, equivalent to 22.9 % of the total generated electric power in Japan. Now nuclear power generation bears a very important role in the stable supply and cost stabilization of electric power. The result of the capacity factor in fiscal year 1984 was 73.9 %, which showed that the nuclear power generation and safety management technologies in Japan are at the top level in the world. However, in order that nuclear power generation accomplishes the role as main power source sufficiently hereafter by increasing the number of plants, the reliability and economical efficiency must be further improved, and especially the safety management and operational management become important. For the purpose, the operational experience accumulated so far must be effectively utilized. In this book, the outline of the administration on the safety regulation of nuclear power generation, the state of operation of nuclear power plants, the state of accidents and failures, the state of regular inspections and so on are summarized. Also the state of radioactive waste management and the radiation control for workers are reported. (Kako, I.)

  2. Nuclear electric power safety, operation, and control aspects

    CERN Document Server

    Knowles, J Brian

    2013-01-01

    Assesses the engineering of renewable sources for commercial power generation and discusses the safety, operation, and control aspects of nuclear electric power From an expert who advised the European Commission and UK government in the aftermath of Three Mile Island and Chernobyl comes a book that contains experienced engineering assessments of the options for replacing the existing, aged, fossil-fired power stations with renewable, gas-fired, or nuclear plants. From geothermal, solar, and wind to tidal and hydro generation, Nuclear Electric Power: Safety, Operation, and Control Aspects ass

  3. Designing nuclear power plants for improved operation and maintenance

    International Nuclear Information System (INIS)

    1996-09-01

    The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig

  4. Designing nuclear power plants for improved operation and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig.

  5. Operation of nuclear power stations during 1975

    International Nuclear Information System (INIS)

    1976-08-01

    In 1975, the production of nuclear energy in the Community of the Nine was 77 thousand million net kWh, an increase of 26.5% over 1974. A short commentry explains this large increase and the situation in each country is briefly reviewed. Then data on the evolution of net production (partitioned according to reactor family), on the availability of reactor types according to their age, and on the structure of nuclear plants (situation at the end of 1975) are presented. The statistical data of annual operation are given for each reactor

  6. Dealing with operational power station wastes

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, R B [Central Electricity Generating Board, London (UK). Nuclear Health and Safety Dept.

    1981-08-01

    The disposal of wastes from nuclear power stations is discussed. Liquid and gaseous wastes, from magnox stations, which are of low level activity, are dispersed to the sea or estuaries on coastal sites or for the case of Trawfynyeld, to the nearby lake. Low activity solid wastes are either disposed of on local authority tips or in shallow land burial sites. Intermediate level wastes, consisting mainly of wet materials such as filter sludges and resins from cooling ponds, are at present stored in shielded storage tanks either dry or under water. Only one disposal route for intermediate waste is used by Britain, namely, sea-dumping. Materials for sea dumping have to be encapsulated in a durable material for example, concrete.

  7. Industrial psychology aspects of power plant operators

    Energy Technology Data Exchange (ETDEWEB)

    Peche, D

    1980-08-01

    The paper gives a survey of the development of the negotiationes that have taken place from the beginning 1976 between representatives of BMI and VDWE to examine whether psychological qualification examinations for the shift personal of nuclear power plants will be appropriate. As a result it is shown that first- and reexaminations shall be carried out according principle 25, the psychological part of this examination should, however, be renounced to a still pending standardisation and testing. The more detailed examination of the sense organs, proposed on this occasion, will be defined by the representatives of VDEW by a new proposal. The routine psychological judgement along with a documentation of the superiors is, however, not considered suitable.

  8. Method of operating a MHD power plant

    International Nuclear Information System (INIS)

    Wysk, S.R.

    1982-01-01

    A fossil fuel is burned substoichiometrically in the combustor of a mhd power plant to produce a high temperature, fuelrich product gas. The product gas is passed through a mhd channel to generate electricity. A reducing agent, preferably natural gas or hydrocarbon, is injected into the fuelrich product gas leaving the mhd generator; and the resulting mixture is held at a temperature in the range of 950 to 1500 0 C for about 1 second to permit the reducing agent to decompose a portion of the nitrogen oxides formed in the combustor. The fuel-rich product gas then passes thru an afterburner wherein combustion is completed and any excess reducing agent is consumed

  9. Stopping power and energy loss cross section of a point charge penetrating through a dense medium of bound electrons

    International Nuclear Information System (INIS)

    Belkacem, A.; Sigmund, P.; Odense Univ.

    1989-01-01

    We have derived the dielectric function ε(k,ω) in the Lindhard approximation for a medium consisting of electrons individually bound by harmonic forces. The dielectric function is expressible in terms of a hypergeometric series and approaches well-known results in the limits of negligible binding, large momentum transfer, and long wavelength, respectively. The stopping power of a moving point charge scales very well with the shifted resonance frequency α 0 = (ω O 2 + ω P 2 ) 1/2 (ω O = oscillator frequency; ω P = plasma frequency) that follows from classical dispersion theory. The results differ noticeably from free-electron behavior even at rather high electron density. The discrete excitation levels of an isolated harmonic oscillator are increasingly shifted and broadened with increasing electron density. 15 refs., 2 figs

  10. Use of wind power forecasting in operational decisions.

    Energy Technology Data Exchange (ETDEWEB)

    Botterud, A.; Zhi, Z.; Wang, J.; Bessa, R.J.; Keko, H.; Mendes, J.; Sumaili, J.; Miranda, V. (Decision and Information Sciences); (INESC Porto)

    2011-11-29

    The rapid expansion of wind power gives rise to a number of challenges for power system operators and electricity market participants. The key operational challenge is to efficiently handle the uncertainty and variability of wind power when balancing supply and demand in ths system. In this report, we analyze how wind power forecasting can serve as an efficient tool toward this end. We discuss the current status of wind power forecasting in U.S. electricity markets and develop several methodologies and modeling tools for the use of wind power forecasting in operational decisions, from the perspectives of the system operator as well as the wind power producer. In particular, we focus on the use of probabilistic forecasts in operational decisions. Driven by increasing prices for fossil fuels and concerns about greenhouse gas (GHG) emissions, wind power, as a renewable and clean source of energy, is rapidly being introduced into the existing electricity supply portfolio in many parts of the world. The U.S. Department of Energy (DOE) has analyzed a scenario in which wind power meets 20% of the U.S. electricity demand by 2030, which means that the U.S. wind power capacity would have to reach more than 300 gigawatts (GW). The European Union is pursuing a target of 20/20/20, which aims to reduce greenhouse gas (GHG) emissions by 20%, increase the amount of renewable energy to 20% of the energy supply, and improve energy efficiency by 20% by 2020 as compared to 1990. Meanwhile, China is the leading country in terms of installed wind capacity, and had 45 GW of installed wind power capacity out of about 200 GW on a global level at the end of 2010. The rapid increase in the penetration of wind power into power systems introduces more variability and uncertainty in the electricity generation portfolio, and these factors are the key challenges when it comes to integrating wind power into the electric power grid. Wind power forecasting (WPF) is an important tool to help

  11. Treatment of operational experience of nuclear power plants in WANO

    International Nuclear Information System (INIS)

    Ibanez, M.

    2013-01-01

    The article describes the activities associated to the Operating Experience Programme of the World Association of Nuclear Operators. The programme manages the event reports submitted by the nuclear power plants to the WANO database for the preparation by the Operating Experience Central Team of some documents like the significant Operating Experience Reports and Significant Event Reports that help the stations to avoid similar events. (Author)

  12. Error analysis of nuclear power plant operator cognitive behavior

    International Nuclear Information System (INIS)

    He Xuhong; Zhao Bingquan; Chen Yulong

    2001-01-01

    Nuclear power plant is a complex human-machine system integrated with many advanced machines, electron devices and automatic controls. It demands operators to have high cognitive ability and correct analysis skill. The author divides operator's cognitive process into five stages to analysis. With this cognitive model, operator's cognitive error is analysed to get the root causes and stages that error happens. The results of the analysis serve as a basis in design of control rooms and training and evaluation of operators

  13. Power-law versus log-law in wall-bounded turbulence: A large-eddy simulation perspective

    Science.gov (United States)

    Cheng, W.; Samtaney, R.

    2014-01-01

    The debate whether the mean streamwise velocity in wall-bounded turbulent flows obeys a log-law or a power-law scaling originated over two decades ago, and continues to ferment in recent years. As experiments and direct numerical simulation can not provide sufficient clues, in this study we present an insight into this debate from a large-eddy simulation (LES) viewpoint. The LES organically combines state-of-the-art models (the stretched-vortex model and inflow rescaling method) with a virtual-wall model derived under different scaling law assumptions (the log-law or the power-law by George and Castillo ["Zero-pressure-gradient turbulent boundary layer," Appl. Mech. Rev. 50, 689 (1997)]). Comparison of LES results for Reθ ranging from 105 to 1011 for zero-pressure-gradient turbulent boundary layer flows are carried out for the mean streamwise velocity, its gradient and its scaled gradient. Our results provide strong evidence that for both sets of modeling assumption (log law or power law), the turbulence gravitates naturally towards the log-law scaling at extremely large Reynolds numbers.

  14. Power-law versus log-law in wall-bounded turbulence: A large-eddy simulation perspective

    KAUST Repository

    Cheng, W.

    2014-01-29

    The debate whether the mean streamwise velocity in wall-bounded turbulent flows obeys a log-law or a power-law scaling originated over two decades ago, and continues to ferment in recent years. As experiments and direct numerical simulation can not provide sufficient clues, in this study we present an insight into this debate from a large-eddy simulation (LES) viewpoint. The LES organically combines state-of-the-art models (the stretched-vortex model and inflow rescaling method) with a virtual-wall model derived under different scaling law assumptions (the log-law or the power-law by George and Castillo [“Zero-pressure-gradient turbulent boundary layer,” Appl. Mech. Rev.50, 689 (1997)]). Comparison of LES results for Re θ ranging from 105 to 1011 for zero-pressure-gradient turbulent boundary layer flows are carried out for the mean streamwise velocity, its gradient and its scaled gradient. Our results provide strong evidence that for both sets of modeling assumption (log law or power law), the turbulence gravitates naturally towards the log-law scaling at extremely large Reynolds numbers.

  15. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1994-06-01

    Quarterly reports on the operation of the Finnish NPPs describe nuclear and radiation safety related events and observations which the Finnish Centre for Radiation and Nuclear Safety considers significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and load factors are also given. One event during the last quarter of 1993 was rated on the International Nuclear Event Scale (INES) as level 1. During this event at Loviisa 2, the secondary circuit emergency feedwater system was erroneously isolated from automatic start-up readiness. The error went unnoticed for 4.5 hours. During 1993 one level 2 incident and three level 1 incidents occurred at the Finnish NPPs. (8 figs., 4 tabs.)

  16. Power MOSFET Thermal Instability Operation Characterization Support

    Science.gov (United States)

    Shue, John L.; Leidecker, Henning

    2010-01-01

    Metal-oxide semiconductor field-effect transistors (MOSFETs) are used extensively in flight hardware and ground support equipment. In the quest for faster switching times and lower "on resistance," the MOSFETs designed from 1998 to the present have achieved most of their intended goals. In the quest for lower on resistance and higher switching speeds, the designs now being produced allow the charge-carrier dominated region (once small and outside of the area of concern) to become important and inside the safe operating area (SOA). The charge-carrier dominated region allows more current to flow as the temperature increases. The higher temperatures produce more current resulting in the beginning of thermal runaway. Thermal runaway is a problem affecting a wide range of modern MOSFETs from more than one manufacturer. This report contains information on MOSFET failures, their causes and test results and information dissemination.

  17. Automation system for operation of nuclear power plant

    International Nuclear Information System (INIS)

    Kinoshita, Mitsuo; Fukuzaki, Koji; Kato, Kanji

    1991-01-01

    The automation system comprises a general monitor control device incorporating a plurality of emergency operation plannings concerning an automatic processing, and judging whether the operation is to be conducted or not depending on the plannings based on the data planed by a plant, a control device for controlling the plant in accordance with the planning when monitor control device judges that the operation should be done due to the emergency operation plannings and an operation planning device aiding the formation of the operation plannings. When the state of the power plant exceeds a normal control region, the reactor power is lowered automatically by so much as a predetermined value or to a predetermined level, to automatically return the plant state to the normal control region. In this way, the plant operation efficiency can be improved. Further, after automatic operation, since operation plannings for recovering original operation plannings are prepared efficiently and recovered operation plannings are started in a short period of time, the operators' burden can be mitigated and power saving can be attained. (N.H.)

  18. Generalizations of the results on powers of -hyponormal operators

    Directory of Open Access Journals (Sweden)

    Ito Masatoshi

    2001-01-01

    Full Text Available Recently, as a nice application of Furuta inequality, Aluthge and Wang (J. Inequal. Appl., 3 (1999, 279–284 showed that "if is a -hyponormal operator for , then is -hyponormal for any positive integer ," and Furuta and Yanagida (Scientiae Mathematicae, to appear proved the more precise result on powers of -hyponormal operators for . In this paper, more generally, by using Furuta inequality repeatedly, we shall show that "if is a -hyponormal operator for , then is -hyponormal for any positive integer " and a generalization of the results by Furuta and Yanagida in (Scientiae Mathematicae, to appear on powers of -hyponormal operators for .

  19. EDP systems for the operational management of nuclear power plant

    International Nuclear Information System (INIS)

    Doerler, R.

    1987-01-01

    An EDP-aided operational management system is to be understood as the total of all organizational conditions (structural organization, procedural organization) and technical means, and is intended to give the individual person a better overview to fulfill his/her responsibilities. The introduction of such a system is aimed at providing the operating personnel with a set of tools matching today's technology for management and administration systems which will enable them to fulfill their tasks in an optimum way. Powerful EDP systems are already used in many nuclear power plants to control and monitor operating processes and to collect and evaluate operational data. (orig./DG) [de

  20. Quality assurance during operation of nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    This Safety Guide provides requirements and recommendations for the establishment and implementation of quality assurance for activities important to safety during commissioning, operation and decommissioning of a nuclear power plant, hereinafter referred to in this Guide as the operation phase or operation. It applies to activities such as: operating, inspecting, testing, commissioning, refuelling, maintaining, repairing, modifying and eventual shut-down and decommissioning of nuclear power plants. It applies also to associated activities related to safety, such as environmental monitoring and responses to emergencies

  1. Analytical modeling of nuclear power station operator reliability

    International Nuclear Information System (INIS)

    Sabri, Z.A.; Husseiny, A.A.

    1979-01-01

    The operator-plant interface is a critical component of power stations which requires the formulation of mathematical models to be applied in plant reliability analysis. The human model introduced here is based on cybernetic interactions and allows for use of available data from psychological experiments, hot and cold training and normal operation. The operator model is identified and integrated in the control and protection systems. The availability and reliability are given for different segments of the operator task and for specific periods of the operator life: namely, training, operation and vigilance or near retirement periods. The results can be easily and directly incorporated in system reliability analysis. (author)

  2. Wind power integration connection and system operational aspects

    CERN Document Server

    Fox, Brendan

    2014-01-01

    Wind Power Integration provides a wide-ranging discussion on all major aspects of wind power integration into electricity supply systems. This second edition has been fully revised and updated to take account of the significant growth in wind power deployment in the past few years. New discussions have been added to describe developments in wind turbine generator technology and control, the network integration of wind power, innovative ways to integrate wind power when its generation potential exceeds 50% of demand, case studies on how forecasting errors have affected system operation, and an update on how the wind energy sector has fared in the marketplace. Topics covered include: the development of wind power technology and its world-wide deployment; wind power technology and the interaction of various wind turbine generator types with the utility network; and wind power forecasting and the challenges faced by wind energy in modern electricity markets.

  3. The operating organization for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  4. The operating organization for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  5. The operating organization for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  6. Optimal Operation of Plug-In Electric Vehicles in Power Systems with High Wind Power Penetrations

    DEFF Research Database (Denmark)

    Hu, Weihao; Su, Chi; Chen, Zhe

    2013-01-01

    in the power systems with high wind power penetrations. In this paper, the integration of plug-in electric vehicles in the power systems with high wind power penetrations is proposed and discussed. Optimal operation strategies of PEV in the spot market are proposed in order to decrease the energy cost for PEV......The Danish power system has a large penetration of wind power. The wind fluctuation causes a high variation in the power generation, which must be balanced by other sources. The battery storage based Plug-In Electric Vehicles (PEV) may be a possible solution to balance the wind power variations...... owners. Furthermore, the application of battery storage based aggregated PEV is analyzed as a regulation services provider in the power system with high wind power penetrations. The western Danish power system where the total share of annual wind power production is more than 27% of the electrical energy...

  7. Use of computer codes to improve nuclear power plant operation

    International Nuclear Information System (INIS)

    Misak, J.; Polak, V.; Filo, J.; Gatas, J.

    1985-01-01

    For safety and economic reasons, the scope for carrying out experiments on operational nuclear power plants (NPPs) is very limited and any changes in technical equipment and operating parameters or conditions have to be supported by theoretical calculations. In the Nuclear Power Plant Scientific Research Institute (NIIAEhS), computer codes are systematically used to analyse actual operating events, assess safety aspects of changes in equipment and operating conditions, optimize the conditions, preparation and analysis of NPP startup trials and review and amend operating instructions. In addition, calculation codes are gradually being introduced into power plant computer systems to perform real time processing of the parameters being measured. The paper describes a number of specific examples of the use of calculation codes for the thermohydraulic analysis of operating and accident conditions aimed at improving the operation of WWER-440 units at the Jaslovske Bohunice V-1 and V-2 nuclear power plants. These examples confirm that computer calculations are an effective way of solving operating problems and of further increasing the level of safety and economic efficiency of NPP operation. (author)

  8. IAEA activity on operator support systems in nuclear power plants

    International Nuclear Information System (INIS)

    Dounaev, V.; Fujita, Y.; Juslin, K.; Haugset, K.; Lux, I.; Naser, J.

    1994-01-01

    Various operator support systems for nuclear power plants are already operational or under development in the IAEA Member States. Operator support systems are based on intelligent data processing and, in addition to plant operation, they are also becoming more important for safety. A key feature of operator support systems is their availability to restructure data to increase its relevance for a given situation. This can improve the user's ability to identify plant mode, system state, and component state and to identify and diagnose faults. Operator support systems can also assist the user in planning and implementing corrective actions to improve the nuclear power plant's availability and safety. In September 1991, the IAEA Committee for Contractual Scientific Services approved the Co-ordinated Research Programme (CRP) on ''Operator Support Systems in Nuclear Power Plants'' in the framework of the Project ''Man-Machine Interface Studies''. The main objective of this programme is to provide guidance and technology transfer for the development and implementation of operator support systems. This includes the experience with human-machine interfaces and closely related issues such as instrumentation and control, the use of computers in nuclear power plants, and operator qualification. (author)

  9. Frequency Control for Island Operation of Bornholm Power System

    DEFF Research Database (Denmark)

    Cha, Seung-Tae; Wu, Qiuwei; Zhao, Haoran

    2014-01-01

    the primary frequency control and the DG units are used to provide the secondary frequency control. As such, the proposed control scheme can strike a balance of the frequency control speed and the energy used from the BESS for the frequency control support. The real-time model of the Bornholm power system......This paper presents a coordinated control strategy of a battery energy storage system (BESS) and distributed generation (DG) units for the island operation of the Danish island of Bornholm. The Bornholm power system is able to transit from the grid connected operation with the Nordic power system...... to the isolated island operation. In order to ensure the secure island operation, the coordinated control of the BESS and the DG has been proposed to stabilize the frequency of the system after the transition to the island operation. In the proposed coordinate control scheme, the BESS is used to provide...

  10. Spanish Power Exchange Market Concepts and Operating Experience

    International Nuclear Information System (INIS)

    Gonzalez, J. J.; Gamito, C.

    2000-01-01

    On January, 1st, 1998, the Spanish Electricity Market started operations. All generators, distributors, commercialization companies, and final consumers negotiate al power exchanges either through the spot market or using bilateral contracts. The Spanish Power Exchange Market Operator (Compania Operadora del Mercado Espanol de electricidad, OMEL) is responsible for the management of the market and for the economic settlement and billing of a transactions on the Power Exchange market, and the technical operational process handled by the System Operator. This paper describes in detail the Spanish market principles and the experience gathered through the design, installation and first two years of market operation. The paper presents also the Spanish market results from January 1998 up to December 1999 indicating each specific market results and aggregate statistics. (Author)

  11. The distribution of wind power forecast errors from operational systems

    Energy Technology Data Exchange (ETDEWEB)

    Hodge, Bri-Mathias; Ela, Erik; Milligan, Michael

    2011-07-01

    Wind power forecasting is one important tool in the integration of large amounts of renewable generation into the electricity system. Wind power forecasts from operational systems are not perfect, and thus, an understanding of the forecast error distributions can be important in system operations. In this work, we examine the errors from operational wind power forecasting systems, both for a single wind plant and for an entire interconnection. The resulting error distributions are compared with the normal distribution and the distribution obtained from the persistence forecasting model at multiple timescales. A model distribution is fit to the operational system forecast errors and the potential impact on system operations highlighted through the generation of forecast confidence intervals. (orig.)

  12. Calculations for accidents in water reactors during operation at power

    International Nuclear Information System (INIS)

    Blanc, H.; Dutraive, P.; Fabrega, S.; Millot, J.P.

    1976-07-01

    The behaviour of a water reactor on an accident occurring as the reactor is normally operated at power may be calculated through the computer code detailed in this article. Reactivity accidents, loss of coolant ones and power over-running ones are reviewed. (author)

  13. New Clean Air Act complicates power plant operation, design

    International Nuclear Information System (INIS)

    Smock, R.W.

    1991-01-01

    In November the president signed into law the new Clean Air Act, ushering in a new era in the power generation industry. This paper reviews the six important sections of the Clean Air Act and their impact on power plant operation and design

  14. 47 CFR 73.51 - Determining operating power.

    Science.gov (United States)

    2010-10-01

    ...'s input power directly from the RF voltage, RF current, and phase angle; or (2) calculating the product of the licensed antenna or common point resistance at the operating frequency (see § 73.54), and... the resistance has been determined. (b) The authorized antenna input power for each station shall be...

  15. Supply, operation and radioactive waste disposal of nuclear power plants

    International Nuclear Information System (INIS)

    Mohrhauer, H.; Krey, M.; Haag, G.; Wolters, J.; Merz, E.; Sauermann, P.F.

    1981-07-01

    The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP) [de

  16. Management for nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    Kueffer, K.

    1981-01-01

    This lecture covers management aspects which have an immediate bearing on safety and identifies the objectives and tasks of management which are required for safe operation of a nuclear power plant and is based on the Codes of Practice and Safety Guides of the IAEA as well as arrangements in use at the Swiss Nuclear Power Station Beznau. (orig./RW)

  17. Vermont Yankee Nuclear Power Station. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 3,560,206 MWh(e) with the reactor on line 7,689 hrs. Information is presented concerning operations power generation, shutdowns, corrective maintenance, primary coolant chemistry, occupational radiation exposure, reportable occurrences, core spray welds inspection, loss of start-up transformer, and union strike

  18. Pilgrim Nuclear Power Station, Unit 1. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 2,587,248 MWH(e) with the reactor on line 6,242.4 hr. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, and reportable occurrences

  19. Market partner orientation in power grid operation; Marktpartnerorientierung im Netzbetrieb

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, Claudia; Gebhardt, Andreas [Buelow und Consorten GmbH, Hamburg (Germany)

    2012-11-15

    Customer orientation is often neglected in power grid operation. Power grid owners have natural monopolies and defined territories and so far had little reason to consider their customers' needs. This is changing with changed boundary conditions. In the competition for concessions and customers for non-regulated services, those grid owners will prevail in the long run wo are aware of their market partners, their power and expectations, and wo are prepared to implement profit-oriented customer orientation measures. (orig.)

  20. Environmental impact assessment of coal power plants in operation

    OpenAIRE

    Bartan Ayfer; Kucukali Serhat; Ar Irfan

    2017-01-01

    Coal power plants constitute an important component of the energy mix in many countries. However, coal power plants can cause several environmental risks such as: climate change and biodiversity loss. In this study, a tool has been proposed to calculate the environmental impact of a coal-fired thermal power plant in operation by using multi-criteria scoring and fuzzy logic method. We take into account the following environmental parameters in our tool: CO, SO2, NOx, particulate matter, fly as...

  1. Experiences of operation for Ikata Nuclear Power Station

    International Nuclear Information System (INIS)

    Kashimoto, Shigeyuki

    1979-01-01

    No. 1 plant in the Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc., is a two-loop PWR unit with electric output of 566 MW, and it began the commercial operation on September 30, 1977, as the first nuclear power station in Shikoku. It is the 13th LWR and 7th PWR in Japan. The period of construction was 52 months since it had been started in June, 1973. During the period, it became the object of the first administrative litigation to seek the cancellation of permission to install the reactor, and it was subjected to the influence of the violent economical variation due to the oil shock, but it was completed as scheduled. After the start of operation, it continued the satisfactory operation, and generated about 2.35 billion KWh for 4300 operation hours. It achieved the rate of utilization of 96.7%. Since March 28, 1978, the first periodical inspection was carried out, and abnormality was not found in the reactor, the steam generator and the fuel at all. The period of inspection was 79 days and shorter than expected. The commercial operation was started again on June 14. The outline of the Ikata Nuclear Power Station, its state of operation, and the periodical inspection are reported. Very good results were able to be reported on the operation for one year, thanks to the valuable experiences offered by other electric power companies. (Kako, I.)

  2. Operator training simulator for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Watanabe, Tadasu

    1988-01-01

    For the operation management of nuclear power stations with high reliability and safety, the role played by operators is very important. The effort of improving the man-machine interface in the central control rooms of nuclear power stations is energetically advanced, but the importance of the role of operators does not change. For the training of the operators of nuclear power stations, simulators have been used from the early stage. As the simulator facilities for operator training, there are the full scope simulator simulating faithfully the central control room of an actual plant and the small simulator mainly aiming at learning the plant functions. For BWR nuclear power stations, two full scope simulators are installed in the BWR Operator Training Center, and the training has been carried out since 1974. The plant function learning simulators have been installed in respective electric power companies as the education and training facilities in the companies. The role of simulators in operator training, the BTC No.1 simulator of a BWR-4 of 780 MWe and the BTC No.2 simulator of a BWR-5 of 1,100 MWe, plant function learning simulators, and the design of the BTC No.2 simulator and plant function learning simulators are reported. (K.I.)

  3. 20 years' operation of the Rheinsberg nuclear power plant

    International Nuclear Information System (INIS)

    Lehmann, R.; Quasniczka, H.; Fiss, W.; Hentschel, G.; Schulz, K.D.

    1986-01-01

    After a 20 years' operation of the Rheinsberg nuclear power plant a review of the operating results achieved, performance of the main equipment, research and development works performed, and experience gained with education and training of plant staff is given. (author)

  4. A note on the Stokes operator and its powers

    KAUST Repository

    Guermond, Jean-Luc; Salgado, Abner

    2010-01-01

    The so-called Stokes operator is an important tool in the analysis of the solutions of the Navier-Stokes equations and their numerical approximation. The aim of this note is to clarify certain properties of the fractional powers of this operator which are sometimes misused. © 2010 Korean Society for Computational and Applied Mathematics.

  5. Centralized operation and monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

    1988-01-01

    According to the prospect of long term energy demand, in 2000, the nuclear power generation facilities in Japan are expected to take 15.9% of the total energy demand. From this fact, it is an important subject to supply nuclear power more stably, and in the field of instrumentation and control, many researches and developments and the incessant effort of improvement have been continued. In the central operation and monitoring system which is the center of the stable operation of nuclear power plants, the man-machine technology aiding operators by electronic and computer application technologies has been positively developed and applied. It is considered that hereafter, for the purpose of rationally heightening the operation reliability of the plants, the high quality man-machine system freely using the most advanced technologies such as high reliability digital technology, optical information transmission, knowledge engineering and so on is developed and applied. The technical trend of operation and monitoring system, the concept of heightening operation and monitoring capability, the upgrading of operation and monitoring system, and the latest operation, monitoring and control systems for nuclear power plants and waste treatment facilities are described. (K.I.)

  6. A note on the Stokes operator and its powers

    KAUST Repository

    Guermond, Jean-Luc

    2010-04-28

    The so-called Stokes operator is an important tool in the analysis of the solutions of the Navier-Stokes equations and their numerical approximation. The aim of this note is to clarify certain properties of the fractional powers of this operator which are sometimes misused. © 2010 Korean Society for Computational and Applied Mathematics.

  7. BN-600 power unit 15-year operating experience

    International Nuclear Information System (INIS)

    Saraev, O.M.; Oshkanov, N.N.; Vylomov, V.V.

    1996-01-01

    Comprehensive experience has been gained with the operating fast reactor BN-600 with a power out of 600 MWe. This paper includes important performance results and gives also an overview of the experience gained from BN-600 NPP commercial operation during 15 years. (author). 2 figs, 1 tab

  8. Aiding operator performance at low power feedwater control

    International Nuclear Information System (INIS)

    Woods, D.D.

    1986-01-01

    Control of the feedwater system during low power operations (approximately 2% to 30% power) is a difficult task where poor performance (excessive trips) has a high cost to utilities. This paper describes several efforts in the human factors aspects of this task that are underway to improve feedwater control. A variety of knowledge acquisition techniques have been used to understand the details of what makes feedwater control at low power difficult and what knowledge and skill distinguishes expert operators at this task from less experienced ones. The results indicate that there are multiple factors that contribute to task difficulty

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

    International Nuclear Information System (INIS)

    Kazushige Hamazaki

    1987-01-01

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

  10. Supporting Control Room Operators in Highly Automated Future Power Networks

    DEFF Research Database (Denmark)

    Chen, Minjiang; Catterson, Victoria; Syed, Mazheruddin

    2017-01-01

    Operating power systems is an extremely challenging task, not least because power systems have become highly interconnected, as well as the range of network issues that can occur. It is therefore a necessity to develop decision support systems and visualisation that can effectively support the hu...... the human operators for decisionmaking in the complex and dynamic environment of future highly automated power system. This paper aims to investigate the decision support functions associated with frequency deviation events for the proposed Web of Cells concept....

  11. Computerized operation manual (COM) of nuclear power plants

    International Nuclear Information System (INIS)

    Szegi, Z.

    1985-01-01

    This paper is to be presented at the International Seminar on Diagnoses of and Response to Abnormal Occurrences at Nuclear Power Plants organized by the International Atomic Energy Agency. The topic of presentation is the Computerized Operational Manual. This system supports the operator at disturbance situations by displaying quickly and unambiguously the operational instructions and the relevant information without mistakes. By the computerized manual the operator can determine the instruction-subsystem which reflects the real state of the power unit. From this point the system guides the operator on how to drive the unit to another determined state by providing the operational instructions at any time. A data bank is also included which contains information concerning rules restricting on maintenance and repair. The system will be realized at Paks NPP. (author)

  12. Operational flexibility and economics of power plants in future low-carbon power systems

    NARCIS (Netherlands)

    Brouwer, Anne Sjoerd; van den Broek, Machteld; Seebregts, Ad; Faaij, André

    2015-01-01

    Future power systems will require large shares of low-carbon generators such as renewables and power plants with Carbon Capture and Storage (CCS) to keep global warming below 2. °C. Intermittent renewables increase the system-wide demand for flexibility and affect the operation of thermal power

  13. Power plant operation and management in a deregulated market

    Energy Technology Data Exchange (ETDEWEB)

    Carraretto, Cristian [Department of Mechanical Engineering, University of Padova, Via Venezia, 1-35131 Padova (Italy)

    2006-05-15

    This paper analyzes the influence of electricity deregulation on the design, operation and management of the power plants owned by strategic and non-strategic producers. After a sensitivity analysis aimed at finding market conditions of profitable operation for thermal and hydroelectric power plants, a Nash-equilibrium market model is used to determine producers' optimum strategies, depending on their relative market power and overall production characteristics. Attention is then focused on the operation of single thermal power plants. Their short-term management plans and consequent effects on emission levels and residual life are described. The available reserve for primary and secondary control deriving from producers' market strategies is discussed. Some design options to improve combined cycles contribution to reserve service are finally described. The paper discusses these problems with a general approach, and uses many cases and examples derived from the current Italian scenario. (author)

  14. Power plant operation and management in a deregulated market

    International Nuclear Information System (INIS)

    Carraretto, Cristian

    2006-01-01

    This paper analyzes the influence of electricity deregulation on the design, operation and management of the power plants owned by strategic and non-strategic producers. After a sensitivity analysis aimed at finding market conditions of profitable operation for thermal and hydroelectric power plants, a Nash-equilibrium market model is used to determine producers' optimum strategies, depending on their relative market power and overall production characteristics. Attention is then focused on the operation of single thermal power plants. Their short-term management plans and consequent effects on emission levels and residual life are described. The available reserve for primary and secondary control deriving from producers' market strategies is discussed. Some design options to improve combined cycles contribution to reserve service are finally described. The paper discusses these problems with a general approach, and uses many cases and examples derived from the current Italian scenario. (author)

  15. Liquid Nitrogen Temperature Operation of a Switching Power Converter

    Science.gov (United States)

    Ray, Biswajit; Gerber, Scott S.; Patterson, Richard L.; Myers, Ira T.

    1995-01-01

    The performance of a 42/28 V, 175 W, 50 kHz pulse-width modulated buck dc/dc switching power converter at liquid nitrogen temperature (LNT) is compared with room temperature operation. The power circuit as well as the control circuit of the converter, designed with commercially available components, were operated at LNT and resulted in a slight improvement in converter efficiency. The improvement in power MOSFET operation was offset by deteriorating performance of the output diode rectifier at LNT. Performance of the converter could be further improved at low temperatures by using only power MOSFET's as switches. The use of a resonant topology will further improve the circuit performance by reducing the switching noise and loss.

  16. Training and qualification of nuclear power plant operators

    International Nuclear Information System (INIS)

    Ohsuga, Y.

    2008-01-01

    Based on training experiences of the nuclear power plant operators of pressurized water reactors (PWR) at the Nuclear Power Training Center Ltd. (NTC) in Japan, training programs were reviewed referring to US training programs. A systematic approach is deployed to them, which mainly consist of on-the-job training and the NTC training courses to meet the needs of all operators from beginners to experienced veterans according to their experiences and objectives. The NTC training is conducted using the simulators that simulate the nuclear power plant dynamics through the use of computers. The operators trained at the NTC work in the central control room of every PWR power plant. The NTC also carries out the qualification examinations for the shift managers. (T. Tanaka)

  17. The new operating conditions of French nuclear power plants

    International Nuclear Information System (INIS)

    Leclercq, J.

    1986-01-01

    Six themes are examined: France's unique position in view of the size of its nuclear operating plant, the role of nuclear power in matching electricity supply to demand, the excellent flexibility provided by PWR facilities in operation, the approaches used in the field of automatic operational control systems, the systematic use of data processing for maintenance and generation and the gains in productivity that can be gained as a result of improving fuel use [fr

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  19. Safety and operation of the Stade nuclear power plant

    International Nuclear Information System (INIS)

    Salcher, H.

    1991-01-01

    The concept of PreussenElektra is to continuously increase the existing safety standard of the Stade nuclear power station using experience gained from faults and operation in nuclear power stations and the progressive state of the art. Modifications to achieve the most gentle operation of the plant have been completed and other are on-going. To do so instruments were attached to those components which are susceptible to fatigue to record the transients and extensive calculatory records were kept. Although the plant has almost 20 years successful operation behind it, it can still stand up well to comparisons with more recent plants as far as safety aspects are concerned. 6 figs

  20. Simplified reactive power management strategy for complex power grids under stochastic operation and incomplete information

    DEFF Research Database (Denmark)

    Vlachogiannis, Ioannis (John)

    2009-01-01

    grids is a major issue for system operators. Under these circumstances an online reactive power management strategy with minimum risk concerning all uncertain and stochastic parameters is proposed. Therefore, new concepts such as reactive power-weighted node-to-node linking and reactive power control......In the current released energy market, the large-scale complex transmission networks and the distribution ones with dispersed energy sources and "intelligent" components operate under uncertainties, stochastic and prior incomplete information. A safe and reliable operation of such complex power...... capability are introduced. A distributed and interconnected stochastic learning automata system is implemented to manage, in a unified and unique way, the reactive power in complex power grids with stochastic reactive power demand and detect the vulnerable part. The proposed simplified strategy can also...

  1. A study on the operator's communication pattern characteristics under abnormal operating situation of nuclear power plants

    International Nuclear Information System (INIS)

    Kim, S. H.; Park, J.

    2008-01-01

    The quality of a probabilistic safety assessment (PSA) has become more important and a human reliability analysis (HRA) is known as a major contributor to the uncertainty of a PSA. As a part of enhancing the HRA quality, a study was initiated to find out characteristics of communication pattern and to evaluate communication quality of the operators of nuclear power plants. Korea Atomic Energy Research Institute (KAERI) is developing evaluation methods for the effect of human-induced events on risk/performance. This paper describes a study on the operator's communication pattern characteristics under abnormal operating situation of nuclear power plants. The study was carried out in four stages; 1) Video recording 2) Audio scripting 3) Message Classification 4) Communication Pattern Analysis. We recorded eight abnormal simulator training programs from Younggwang nuclear power plant training center. After that we performed message classification and carried out communication pattern analysis. We compared communication patterns of abnormal operating situation with emergency operating situation.As results of analysis, the role of SRO (senior reactor operator) under abnormal operating situation was decreased than the activities under emergency operating situation because each operator (reactor operator, turbine operator, safety supervisor) in main control room (MCR) performs the activity to control by himself with corresponding field engineers with his basic knowledge of the system. On the other hand, the operator's decision making processes and activities under abnormal operating situation were dramatically increased than the emergency operating situation. (authors)

  2. An analysis of nuclear power plant operating costs

    International Nuclear Information System (INIS)

    1988-01-01

    This report presents the results of a statistical analysis of nonfuel operating costs for nuclear power plants. Most studies of the economic costs of nuclear power have focused on the rapid escalation in the cost of constructing a nuclear power plant. The present analysis found that there has also been substantial escalation in real (inflation-adjusted) nonfuel operating costs. It is important to determine the factors contributing to the escalation in operating costs, not only to understand what has occurred but also to gain insights about future trends in operating costs. There are two types of nonfuel operating costs. The first is routine operating and maintenance expenditures (O and M costs), and the second is large postoperational capital expenditures, or what is typically called ''capital additions.'' O and M costs consist mainly of expenditures on labor, and according to one recently completed study, the majoriy of employees at a nuclear power plant perform maintenance activities. It is generally thought that capital additions costs consist of large maintenance expenditures needed to keep the plants operational, and to make plant modifications (backfits) required by the Nuclear Regulatory Commission (NRC). Many discussions of nuclear power plant operating costs have not considered these capital additions costs, and a major finding of the present study is that these costs are substantial. The objective of this study was to determine why nonfuel operating costs have increased over the past decade. The statistical analysis examined a number of factors that have influenced the escalation in real nonfuel operating costs and these are discussed in this report. 4 figs, 19 tabs

  3. Operating history of U.S. nuclear power reactors

    International Nuclear Information System (INIS)

    1974-01-01

    The operating history of U. S. nuclear power plants through December 31, 1974 has been collected. Included are those nuclear reactor facilities which produce electricity, even if in token amounts, or which are part of a development program concerned with the generation of electricity through the use of a nuclear reactor as a heat source. The information is based on data furnished by facility operators. The charts are plotted in terms of cumulative thermal energy as a function of time. Since only those shutdowns of five days or more are shown, the charts do not give a detailed history of plant operation. They do, however, give an overview of the operating history of a variety of developmental and experimental nuclear power reactors. The data show the yearly gross generation of electricity for each U. S. nuclear plant and, for civilian power plants, information on reactor availability and plant capacity factor. (U.S.)

  4. Operational results in the Onagawa Nuclear Power Station

    International Nuclear Information System (INIS)

    Hasegawa, Kanichi; Kato, Katsuya; Terada, Hideo; Kamata, Takakage; Kaimura, Yoshiharu

    1986-01-01

    In the Onagawa Nuclear Power Station, Unit 1 (BWR type, with electric output 524 MW) started operation in June 1, 1984. The power plant has then continued non-stop operation up to April 2, 1985, thus exhibiting its base load plant. In fiscal 1984, the continuous operation is for 342 days; the capacity factor is about 96.1 %, which is the world's top. During the period, the radioactivity releases to the environment in both liquid and gaseous wastes are below the detection limits. The collective exposure dose for plant personnel is merely 6 man-rem. Subsequently, its 1st periodical inspection was started on April 3, 1985, and finished in July the same year. So, the power plant is now again in operation. (Mori, K.)

  5. Safeguard management for operation security in nuclear power plants (NPPs)

    International Nuclear Information System (INIS)

    Woo, Tae-Ho; Lee, Un-Chul

    2011-01-01

    Safeguard modeling is conducted for the successful operations in the nuclear power plants (NPPs). The characteristics of the secure operation in NPPs are investigated using the network effect method which is quantified by the Monte-Carlo algorithm. Fundamentally, it is impossible to predict the exact time of a terror incident. So, the random sampling for the event frequency is a reasonable method, including the characteristics of network effect method such as the zero-sum quantification. The performance of operation with safeguard is the major concern of this study. There are three kinds of considerations as the neutronics, thermo-hydraulics, and safeguard properties which are organized as an aspect of safeguard considerations. The result, therefore, can give the stability of the operations when the power is decided. The maximum value of secure operation is 12.0 in the third month and the minimum value is 1.0 in the 18th and 54th months, in a 10 years period. Thus, the stability of the secure power operation increases 12 times higher than the lowest value according to this study. This means that the secure operation is changeable in the designed NPPs and the dynamical situation of the secure operation can be shown to the operator.

  6. Nuclear power plant life management and longer-term operation

    International Nuclear Information System (INIS)

    2006-01-01

    This book, prepared by NEA member country experts, contains data and analyses relevant to nuclear power plant life management and the plants' extended, longer-term operation (LTO). It addresses technical, economic and environmental aspects and provides insights into the benefits and challenges of plant life management and LTO. It will be of interest to policy makers and senior managers in the nuclear power sector and governmental bodies involved in nuclear power programme design and management. The data and information on current trends in nuclear power plant life management will be useful to researchers and analysts working in the field of nuclear energy system assessment. (authors)

  7. A series of lectures on operational physics of power reactors

    International Nuclear Information System (INIS)

    Mohanakrishnan, P.; Rastogi, B.P.

    1982-01-01

    This report discusses certain aspects of operational physics of power reactors. These form a lecture series at the Winter College on Nuclear Physics and Reactors, Jan. - March 1980, conducted at the International Centre for Theoretical Physics, Trieste, Italy. The topics covered are (a) the reactor physics aspects of fuel burnup (b) theoretical methods applied for burnup prediction in power reactors (c) interpretation of neutron detector readings in terms of adjacent fuel assembly powers (d) refuelling schemes used in power reactors. The reactor types chosen for the discussion are BWR, PWR and PHWR. (author)

  8. Operational margin monitoring system for boiling water reactor power plants

    International Nuclear Information System (INIS)

    Fukutomi, S.; Takigawa, Y.

    1992-01-01

    This paper reports on an on-line operational margin monitoring system which has been developed for boiling water reactor power plants to improve safety, reliability, and quality of reactor operation. The system consists of a steady-state core status prediction module, a transient analysis module, a stability analysis module, and an evaluation and guidance module. This system quantitatively evaluates the thermal margin during abnormal transients as well as the stability margin, which cannot be evaluated by direct monitoring of the plant parameters, either for the current operational state or for a predicted operating state that may be brought about by the intended operation. This system also gives operator guidance as to appropriate or alternate operations when the operating state has or will become marginless

  9. Research on wind power grid-connected operation and dispatching strategies of Liaoning power grid

    Science.gov (United States)

    Han, Qiu; Qu, Zhi; Zhou, Zhi; He, Xiaoyang; Li, Tie; Jin, Xiaoming; Li, Jinze; Ling, Zhaowei

    2018-02-01

    As a kind of clean energy, wind power has gained rapid development in recent years. Liaoning Province has abundant wind resources and the total installed capacity of wind power is in the forefront. With the large-scale wind power grid-connected operation, the contradiction between wind power utilization and peak load regulation of power grid has been more prominent. To this point, starting with the power structure and power grid installation situation of Liaoning power grid, the distribution and the space-time output characteristics of wind farm, the prediction accuracy, the curtailment and the off-grid situation of wind power are analyzed. Based on the deep analysis of the seasonal characteristics of power network load, the composition and distribution of main load are presented. Aiming at the problem between the acceptance of wind power and power grid adjustment, the scheduling strategies are given, including unit maintenance scheduling, spinning reserve, energy storage equipment settings by the analysis of the operation characteristics and the response time of thermal power units and hydroelectric units, which can meet the demand of wind power acceptance and provide a solution to improve the level of power grid dispatching.

  10. Power System Operation with Large-Scale Wind Power in Liberalised Environments

    International Nuclear Information System (INIS)

    Ummels, B.C.

    2009-01-01

    The disadvantages of producing electricity from fossil fuels are that their supply is finite and unevenly distributed across the earth. Conventional power stations also emit greenhouse gases. Therefore, sustainable alternatives must be developed, such as wind power. The disadvantages of wind are that it may or may not blow and that it is unpredictable. Th generation of electricity must however always equal the consumption. This makes the integration of wind power in the electricity system more difficult. This thesis investigates the integration of wind power into the existing power system. Simulation models are developed and used to explore the operation of power systems with a lot of wind power. The simulations provide a picture of the reliability, cost and emission of CO2 of the generation of electricity, with and without wind power. The research also takes into account electricity exchange on international markets. Possible solutions for integrating wind power, such as flexible power plants and energy storage, are investigated as well

  11. Nuclear power plant operation experience - a feedback programme

    International Nuclear Information System (INIS)

    Banica, I.; Sociu, F.; Margaritescu, C.

    1994-01-01

    An effective high quality maintenance programme is required for the safe reliable operation of a nuclear power plant. To achieve the objectives of such a programme, both plant management and staff must be highly dedicated and motivated to perform high quality work at all levels. Operating and maintenance experience data collections and analysis are necessary in order to enhance the safety of the plant and reliability of the structures systems and components throughout their operating life. Significant events, but also minor incident, may reveal important deficiencies or negative trends adverse to safety. Therefore, a computer processing system for collecting, classifying and evaluating abnormal events or findings concerning operating-maintenance and for feeding back the results of the lessons learned from experience into the design and the operation of our nuclear power plant is considered to be of paramount importance. (Author)

  12. Island operation - modelling of a small hydro power system

    Energy Technology Data Exchange (ETDEWEB)

    Skarp, Stefan

    2000-02-01

    Simulation is a useful tool for investigating a system behaviour. It is a way to examine operating situations without having to perform them in reality. If someone for example wants to test an operating situation where the system possibly will demolish, a computer simulation could be a both cheaper and safer way than to do the test in reality. This master thesis performs and analyses a simulation, modelling an electronic power system. The system consists of a minor hydro power station, a wood refining industry, and interconnecting power system components. In the simulation situation the system works in a so called island operation. The thesis aims at making a capacity analysis of the current system. Above all, the goal is to find restrictions in load power profile of the consumer, under given circumstances. The computer software used in simulations is Matlab and its additional program PSB (Power System Blockset). The work has been carried out in co-operation with the power supplier Skellefteaa Kraft, where the problem formulation of this master thesis was founded.

  13. Operating Experience at the Aagesta Nuclear Power Station

    International Nuclear Information System (INIS)

    Sandstroem, S.

    1966-09-01

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW t ) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965

  14. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S [ed.

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

  15. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S. (ed.)

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

  16. Economic evaluation of nuclear reactor operation utilizing power effect

    International Nuclear Information System (INIS)

    Budinsky, M.; Mydliar, J.

    1988-01-01

    The operation of a reactor at the so-called power effect may substantially increase the burnup of fuel to be removed. The aim of the evaluation of such reactor operation is the optimal determination of the time over which the yield of the higher use of fuel exceeds economic losses resulting from the increased share of constant expenditure of the price of generated kWh of electric power which ensues from such operation. A mathematical model is presented for such evaluation of reactor operation with regard to benefits for the national economy which is the basis of the ESTER 2 computer program. The calculations show that the prices of generated and delivered kWh are minimally 2% less than the prices of generated power without the power effect use. The minimum ranges in the interval of 30 to 50 days. The dependence of the price of generated and delivered kWh from the point of view of the operator of the power plant as well as the component of fuel price of generated kWh will not reach the minimum even after 50 days of operation. From the operating and physical points of view the duration of power effect is not expected to exceed 20 to 30 days which means that from the point of view of the national economy the price of generated and delivered kWh will be 1.6 to 2% less and the fuel component of the price of the generated kWh will be 3 to 4.5% lower. (Z.M.). 5 figs., 3 refs

  17. Shutdown and low-power operation at commercial nuclear power plants in the United States

    International Nuclear Information System (INIS)

    1993-09-01

    The report contains the results of the NRC Staff's evaluation of shutdown and low-power operations at US commercial nuclear power plants. The report describes studies conducted by the staff in the following areas: Operating experience related to shutdown and low-power operations, probabilistic risk assessment of shutdown and low-power conditions and utility programs for planning and conducting activities during periods the plant is shut down. The report also documents evaluations of a number of technical issues regarding shutdown and low-power operations performed by the staff, including the principal findings and conclusions. Potential new regulatory requirements are discussed, as well as potential changes in NRC programs. A draft report was issued for comment in February 1992. This report is the final version and includes the responses to the comments along with the staff regulatory analysis of potential new requirements

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

    International Nuclear Information System (INIS)

    2006-06-01

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

  19. Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-10-15

    At the beginning of 1963 nuclear power plants produced some 3 500 000kW of electrical power to different distribution grids around the world. Much significant operating experience has been gained with these power reactors, but this experience is often not collected in such a way as to make it easily available. The International Atomic Energy Agency convened a Conference on Operating Experience with Power Reactors in Vienna from 4-8 June 1963 which was attended by 240 participants representing 27 of the Agency's Member States and six international organizations. At the Conference, 42 papers giving detailed experience with more than 20 nuclear power stations were discussed. Although similar meetings on a national or regional scale have been held earlier in various countries, this is the first arranged by the Agency on a world-wide basis. Some of the detailed material may have been given earlier but for the most part it represents new and recently acquired experience, and for the first time it has been possible to compile in one place such extensive material on the operating experience with power reactors. The Conference discussed the experience gained both generally in the context of national and international nuclear power development programmes, and more specifically in the detailed operating experience with different power reactor stations. In addition, various plant components, fuel cycles, staffing of nuclear plants and licensing of such staff were treated. It is hoped that these Proceedings will be of interest not only to nuclear plant designers and operators who daily encounter problems similar to those discussed by the Conference, but also to those guiding the planning and implementation of power development programmes.

  20. Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-10-15

    At the beginning of 1963 nuclear power plants produced some 3 500 000 kW of electrical power to different distribution grids around the world. Much significant operating experience has been gained with these power reactors, but this experience is often not collected in such a way as to make it easily available. The International Atomic Energy Agency convened a Conference on Operating Experience with Power Reactors in Vienna from 4 -8 June 1963 which was attended by 240 participants representing 27 of the Agency's Member States and six international organizations. At the Conference, 42 papers giving detailed experience with more than 20 nuclear power stations were discussed. Although similar meetings on a national or regional scale have been held earlier in various countries, this is the first arranged by the Agency on a world-wide basis. Some of the detailed material may have been given earlier but for the most part it represents new and recently acquired experience, and for the first time it has been possible to compile in one place such extensive material on the operating experience with power reactors. The Conference discussed the experience gained both generally in the context of national and international nuclear power development programmes, and more specifically in the detailed operating experience with different power reactor stations. In addition, various plant components, fuel cycles, staffing of nuclear plants and licensing of such staff were treated. It is hoped that these Proceedings will be of interest not only to nuclear , plant designers and operators who daily encounter problems similar to those discussed by the Conference, but also to those guiding the planning and implementation of power development programmes.

  1. Selection/licensing of nuclear power plant operators

    International Nuclear Information System (INIS)

    Saari, L.M.

    1983-07-01

    An important aspect of nuclear power plant (NPP) safety is the reactor operator in the control room. The operators are the first individuals to deal with an emergency situation, and thus, effective performance on their part is essential for safe plant operations. Important issues pertaining to NPP reactor operators would fall within the personnel subsystem of our safety system analysis. While there are many potential aspects of the personnel subsystem, a key first step in this focus is the selection of individuals - attempting to choose individuals for the job of reactor operator who will safely perform the job. This requires a valid (job-related) selection process. Some background information on the Nuclear Regulatory Commission (NRC) licensing process used for selecting NPP reactor operators is briefly presented and a description of a research endeavor now underway at Battelle for developing a valid reactor operator licensing examination is included

  2. Simulation bounds for system availability

    International Nuclear Information System (INIS)

    Tietjen, G.L.; Waller, R.A.

    1976-01-01

    System availability is a dominant factor in the practicality of nuclear power electrical generating plants. A proposed model for obtaining either lower bounds or interval estimates on availability uses observed data on ''n'' failure-to-repair cycles of the system to estimate the parameters in the time-to-failure and time-to-repair models. These estimates are then used in simulating failure/repair cycles of the system. The availability estimate is obtained for each of 5000 samples of ''n'' failure/repair cycles to form a distribution of estimates. Specific percentile points of those simulated distributions are selected as lower simulation bounds or simulation interval bounds for the system availability. The method is illustrated with operational data from two nuclear plants for which an exponential time-to-failure and a lognormal time-to-repair are assumed

  3. Improvements in operational safety performance of the Magnox power stations

    Energy Technology Data Exchange (ETDEWEB)

    Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)

    2000-10-01

    In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

  4. ANALYSIS OF OPTIMUM OPERATING MODES OF POWER TRANSFORMERS UNDER OPERATING CONDITIONS

    Directory of Open Access Journals (Sweden)

    I. V. Khomenko

    2016-12-01

    Full Text Available Purpose. The study of parallel operation optimal modes of transformer equipment for a variety of operating conditions: same or different types of transformers, with or without reactive power flows. Methodology. Losses of energy in transformers make 30 % of all losses. Therefore the choice of the economically justified parallel operation of transformers is effective action to reduce losses. Typically, in the calculations of reactive power flows in the transformers are not taken into account. It is interesting to analyze the optimal operating conditions of transformers with and without reactive power flows. Results. Calculations for transformers in distribution networks showed that the inclusion of reactive power flows in transformers significant impact on the calculated optimum regimes of transformers.

  5. Implementation of an operator model with error mechanisms for nuclear power plant control room operation

    International Nuclear Information System (INIS)

    Suh, Sang Moon; Cheon, Se Woo; Lee, Yong Hee; Lee, Jung Woon; Park, Young Taek

    1996-01-01

    SACOM(Simulation Analyser with Cognitive Operator Model) is being developed at Korea Atomic Energy Research Institute to simulate human operator's cognitive characteristics during the emergency situations of nuclear power plans. An operator model with error mechanisms has been developed and combined into SACOM to simulate human operator's cognitive information process based on the Rasmussen's decision ladder model. The operational logic for five different cognitive activities (Agents), operator's attentional control (Controller), short-term memory (Blackboard), and long-term memory (Knowledge Base) have been developed and implemented on blackboard architecture. A trial simulation with a scenario for emergency operation has been performed to verify the operational logic. It was found that the operator model with error mechanisms is suitable for the simulation of operator's cognitive behavior in emergency situation

  6. A Real-Time Simulation Platform for Power System Operation

    DEFF Research Database (Denmark)

    Cha, Seung-Tae; Østergaard, Jacob; Wu, Qiuwei

    2010-01-01

    This paper describes the real-time digital simulation platform that can be used for power system operation, analysis, and power system modeling. This particular platform gives grid operators, planners and researchers the opportunity to observe how a power system behaves and can be used...... in real time. Various phenomena commonly encountered when dealing with the two-area system is studied. Despite its small size, it mimics very closely the behavior of typical systems in actual operation. The electromagnetic transient type of simulation made in RSCAD enables the study of fast and detailed...... phenomena like single-phase faults in the two-area network and to observe their effects on a larger time scale. Also, the case study of 11 bus system with 5 generators has been also used and the results are presented....

  7. Operational experience, availability and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    Kueffer, K.

    1980-01-01

    This lecture - presents a survey on nuclear power production and plant performance in the Western World covering all reactor types and light-water reactors in particular and discusses key parameters such as load factors and non-availability analysis. - outlines the main reasons for the reliable performance of Swiss nuclear power plants - quality equipment - operator qualification and training - engineering know how on site - maintenance philosophy and outage planning - information system and feedback of experience - explains the management functions as applied at the Beznau Nuclear Power Station to ensure high power productivity and reliability - improvement - a feedback control system - analysis of production losses - optimization in shut-down planning - minimizing disturbances during plant operation - optimizing personnel qualification and efficiency. (orig.)

  8. Improving nuclear power plant safety through operator aids

    International Nuclear Information System (INIS)

    1987-12-01

    In October 1986, the IAEA convened a one-week Technical Committee Meeting on Improving Nuclear Power Plant Safety Through Operator Aids. The term ''operator aid'' or more formally ''operator support system'' refers to a class of devices designed to be added to a nuclear power plant control station to assist an operator in performing his job and thereby decrease the probability of operator error. The addition of a carefully planned and designed operator aid should result in an increase in nuclear power plant safety and reliability. Operator aids encompass a wide range of devices from the very simple, such as color coding a display to distinguish it out of a group of similar displays, to the very complex, such as a computer-generated video display which concentrates a number of scattered indicator readings located around a control room into a concise display in front of the operator. This report provides guidelines and information to help make a decision as to whether an operator aid is needed, what kinds of operator aids are available and whether it should be purchased or developed by the utility. In addition, a discussion is presented on advanced operator aids to provide information on what may become available in the future. The broad scope of these guidelines makes it most suitable for use by a multi-disciplinary team. The document consists of two parts. The recommendations and results of the meeting discussions are given in the first part. The second part is the annex where the papers presented at the Technical Committee Meeting are printed. A separate abstract was prepared for each of the 10 papers. Refs, figs and tabs

  9. US nuclear power plant operating cost and experience summaries

    International Nuclear Information System (INIS)

    Kohn, W.E.; Reid, R.L.; White, V.S.

    1998-02-01

    NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov)

  10. US nuclear power plant operating cost and experience summaries

    Energy Technology Data Exchange (ETDEWEB)

    Kohn, W.E.; Reid, R.L.; White, V.S.

    1998-02-01

    NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov).

  11. Operation of the power system 2011; Driften av kraftsystemet 2011

    Energy Technology Data Exchange (ETDEWEB)

    Brekke, Karstein; Ulsberg, Helge

    2012-07-01

    This report has been prepared as a result of the allotment letters for 2012 to the Norwegian Water Resources and Energy Directorate (NVE) of Petroleum and Energy (MPE), which imposes NVE to prepare an annual report on the operation of the power system. The report shall include information and analysis related to the state of the power system, including errors in key transmission links within Norway and abroad. (Author)

  12. Selected financial and operating ratios of public power systems

    International Nuclear Information System (INIS)

    Moody, D.

    1993-01-01

    In 1992, the American Public Power Association published its fourth report on financial and operating ratios. Based on 1990 data for the largest public power distribution systems, the report examined 21 categories of ratio indicators that can be used by public power distribution systems to assess their performance relative to the utilities of of comparable size and in the same geographic region. The 394 utilities summarized in the report are those that are required to file financial statements with the Energy Information Administration (EIA). Ratios were calculated from financial and operating data reported by utilities to the EIA. Data are presented for the following ratios: (1) revenue per kW/hr; (2) revenue for customer; (3) debt to total assets; (4) operating ratio; (5) current ratio; (6) times interest earned; (7) net income per revenue dollar; (8) uncollectible accounts per revenue dollar; (9) retail MW hr sales per manpower generation employee; (10) retail customers per nonpower generation employee; (11) total operation and maintenane expense per kW hr sold; (12) total operation and maintenance expense per retail customer; (13) total power supply expense kW hr sold; (14) purchased power cost per kW hr; (15) production expense per not kW hr; (16) retail customers for with reader; (17) distribution operation and maintenance expenses per retail customer; (18) distribution operation and maintenance expenses per circuit mile; (19) customer accounting, customer service and sales expenses per retail customers; (20) administration and general expenses per retail customer; (21) labor expense per worker-hour; (22) OSHA incidence rate; and (23) the system average interruptible duration index

  13. Nuclear power plant operating experience. Annual report, 1978

    International Nuclear Information System (INIS)

    Beebe, M.R.

    1979-12-01

    This report is the fifth in a series of reports issued annually that summarizes the operating experience of US nuclear power plants in commercial operation. Power generation statistics, plant outages, reportable occurrences, fuel element performance, occupational radiation exposure for each plant are presented. Summary highlights of these areas are discussed. The report includes 1978 data from 65 plants - 25 boiling water reactor plants and 40 pressurized water reactor plants. Discussion of radioactive effluents which has been a part of this report in previous years, has not been included in this issue because of late acquisition of data

  14. Optimum operation of a small power production facility

    Energy Technology Data Exchange (ETDEWEB)

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

    1983-09-01

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

  15. Inertial Fusion Power Plant Concept of Operations and Maintenance

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-01-15

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

  16. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  17. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  18. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  19. Radiation protection during operation of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    This Guide describes a Radiation Protection Programme for nuclear power plants. It includes: (1) An outline of the basic principles as well as practical aspects of the programme; (2) A description of the responsibilities of the operating organization to establish an effective programme based upon these principles; (3) A description of the administrative and technical measures to establish and implement the programme. This Guide also deals with the operational aspects to be considered by the operating organization in reviewing design in order to facilitate implementation of the Radiation Protection Programme. This Guide covers the requirements for a Radiation Protection Programme for all operational states of the nuclear power plant. It also includes guidelines for handling planned special exposures and for coping with unplanned exposures and contamination of personnel, areas, and equipment. Additional information concerning emergency situations involving releases of radioactive materials is given in Safety Guides 50-SG-O6, ''Preparedness of the Operating Organization (Licensee) for Emergencies at Nuclear Power Plants'', and 50-SG-G6, ''Preparedness of Public Authorities for Emergencies at Nuclear Power Plants''. This Guide covers the principles of dose limitation to site personnel and to the public, but it does not include detailed instructions on the techniques used for the actual measurement and evaluation of the exposures. This Guide does not include detailed instructions on environmental surveys, but it does mention principal steps in environmental monitoring which may be required for confirmation of the acceptability of radioactive discharges

  20. Assuring human operator alertness at night in power plants

    International Nuclear Information System (INIS)

    Moore-Ede, M.C.

    1988-01-01

    The human body is not designed for peak alertness and performance at night, nor is it well-equipped to cope with the frequent day-night inversions required by rotating shift work schedules. As a result, the human operator can become the weak link in a complex technological operation such as a nuclear power plant. The high degree of dependence on human operator vigilance, decision-making ability and performance that is required in nuclear power plant operations can conflict with the human sleepiness and error-proneness which naturally occur during the night shift or after extended periods without adequate sleep. An opportunity to address these problems has come from a series of major research advances in basic circadian physiology

  1. Operational limits and conditions for nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It covers the concept of operational limits and conditions, their content as applicable to various types of thermal reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The principles of the operational limits and conditions are established in section 3 of the Agency's Code of Practice on Safety in Nuclear Power Plant Operation, including Commissioning and Decommissioning (IAEA Safety Series No. 50-C-O), which this present Safety Guide supplements. In order to present all pertinent information in this Guide, the provisions of section 3 of the Code are repeated

  2. Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math

    Directory of Open Access Journals (Sweden)

    Fang Xiang

    2011-01-01

    Full Text Available This paper makes use of the concept and theory of fuzzy number in fuzzy mathematics, to research for the response time of operator in accident of Chinese nuclear power plant. Through the quantitative analysis for the performance shape factors (PSFs which influence the response time of operators, the formula of the operator response time is obtained based on the possibilistic fuzzy linear regression model which is used for the first time in this kind of research. The research result shows that the correct research method can be achieved through the analysis of the information from a small sample. This method breaks through the traditional research method and can be used not only for the reference to the safe operation of nuclear power plant, but also in other areas.

  3. Higher operational safety of nuclear power plants by evaluating the behaviour of operating personnel

    International Nuclear Information System (INIS)

    Mertins, M.; Glasner, P.

    1990-01-01

    In the GDR power reactors have been operated since 1966. Since that time operational experiences of 73 cumulative reactor years have been collected. The behaviour of operating personnel is an essential factor to guarantee the safety of operation of the nuclear power plant. Therefore a continuous analysis of the behaviour of operating personnel has been introduced at the GDR nuclear power plants. In the paper the overall system of the selection, preparation and control of the behaviour of nuclear power plant operating personnel is presented. The methods concerned are based on recording all errors of operating personnel and on analyzing them in order to find out the reasons. The aim of the analysis of reasons is to reduce the number of errors. By a feedback of experiences the nuclear safety of the nuclear power plant can be increased. All data necessary for the evaluation of errors are recorded and evaluated by a computer program. This method is explained thoroughly in the paper. Selected results of error analysis are presented. It is explained how the activities of the personnel are made safer by means of this analysis. Comparisons with other methods are made. (author). 3 refs, 4 figs

  4. Nuclear power costs in the build, operate, transfer approach

    International Nuclear Information System (INIS)

    Aybers, M.N.; Sahin, B.

    1990-01-01

    The costs of nuclear power are discussed with special reference to the economic problems faced by developing countries, and the relative merit of a new accounting approach, viz., the build, operate, transfer contract model, which was proposed in Turkey for the Akkuyu nuclear power project, is illustrated. In this context, the general methodology of calculating nuclear power costs is summarized and a capital cost analysis for a 986 MW pressurized water reactor plant is given in terms of constant monetary units for the above contract model and the turnkey contract model. Adjustment of the costs taking into account regional conditions such as inflation and higher interest rates is also indicated. (orig.) [de

  5. Control of operational transients in power reactors - Methodology

    International Nuclear Information System (INIS)

    Vukovic, D.

    1983-01-01

    By introducing the nuclear power stations in the electric power system, questions of their possibilities to satisfy system's demand arise. Control of operational transients (temperature and Xe 135 ) in power reactors by determining the optimal control rod strategy is given. Ti optimize the Xe 135 transients, the Pantryagin theorem of optimal processes is applied. For solving three dimensional, two-group diffusion equations the heterogeneous Feinberg-Galanin method with axial flux harmonics is adopted. An application of this formalism to three-dimensional, finite cylindrical pressurised water reactor radially reflected is presented. (author)

  6. Independent verification in operations at nuclear power plants

    International Nuclear Information System (INIS)

    Donderi, D.C.; Smiley, A.; Ostry, D.J.; Moray, N.P.

    1995-09-01

    A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries, was conducted for this study. This report identifies the uses of independent verification and provides an assessment of the effectiveness of the various approaches. The findings indicate that at Canadian nuclear power plants as much, if not more, independent verification is performed than at power plants in the other countries included in the study. Additional requirements in this area are not proposed for Canadian stations. (author)

  7. Study on training of nuclear power system operators

    International Nuclear Information System (INIS)

    Guo Lifeng; Zhou Gang; Yu Lei

    2012-01-01

    In order to satisfy new requirements about operators of nuclear power system, which are brought up by development and changes of social environment, science and technology, we do research on and make analysis of the problem of operator training. This paper focuses on development and changes of operator training system and content, mentality training, application of new technology to training, feedback of experience and so on. Analysis showed that the content of operator training is also confronted with some new requirements. So we bring up the new requirements to the operator, such as mentality training, cognizance ability training, adaptability training of special environment and endurance training. Besides, it is important for perfecting operator cultivation mechanism and improving training effect to feed back experience and apply new technology. So the trainer must improve training content and cultivation mechanism continuously. (authors)

  8. Operation and technology of high pulsed power generators

    International Nuclear Information System (INIS)

    Eyl, P.; Romary, P.

    1995-01-01

    In order to satisfy the needs of ''components and electronic circuits hardness'', a range of high pulsed power generators is available in the French Atomic Energy Commission. The goal of this paper is to present the general principles of operation and the main characteristics of the irradiation facilities which are operational at the CESTA center. Finally, we give a brief outline of the new technology developments. (authors). 6 refs., 16 figs

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

    International Nuclear Information System (INIS)

    Chen Sen

    2005-01-01

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

  10. Inspection during operation of a nuclear power plant in Spain

    International Nuclear Information System (INIS)

    Gutierrez Bernal, R.

    1977-01-01

    The control and surveillance activities, as well as the operating data and results of the three nuclear power plants presently in operation: Jose Cabrera, Santa Maria de Garona and Vandellos, are summarized. The first two are light-water type, with different pressure and boiling characteristics and the third is of the gas-graphite type. The main aspects, from an inspection point of view, of the experience obtained in these three plants are analyzed. (author) [es

  11. Personality Factors and Nuclear Power Plant Operators: Initial License Success

    Science.gov (United States)

    DeVita-Cochrane, Cynthia

    Commercial nuclear power utilities are under pressure to effectively recruit and retain licensed reactor operators in light of poor candidate training completion rates and recent candidate failures on the Nuclear Regulatory Commission (NRC) license exam. One candidate failure can cost a utility over $400,000, making the successful licensing of new operators a critical path to operational excellence. This study was designed to discover if the NEO-PI-3, a 5-factor measure of personality, could improve selection in nuclear utilities by identifying personality factors that predict license candidate success. Two large U.S. commercial nuclear power corporations provided potential participant contact information and candidate results on the 2014 NRC exam from their nuclear power units nation-wide. License candidates who participated (n = 75) completed the NEO-PI-3 personality test and results were compared to 3 outcomes on the NRC exam: written exam, simulated operating exam, and overall exam result. Significant correlations were found between several personality factors and both written and operating exam outcomes on the NRC exam. Further, a regression analysis indicated that personality factors, particularly Conscientiousness, predicted simulated operating exam scores. The results of this study may be used to support the use of the NEO-PI-3 to improve operator selection as an addition to the current selection protocol. Positive social change implications from this study include support for the use of a personality measure by utilities to improve their return-on-investment in candidates and by individual candidates to avoid career failures. The results of this study may also positively impact the public by supporting the safe and reliable operation of commercial nuclear power utilities in the United States.

  12. Fort St. Vrain reactor performance and operation to full power

    International Nuclear Information System (INIS)

    Simon, W.A.; Bramblett, G.C.

    1982-01-01

    The Fort St. Vrain Nuclear Generating Station, powered by a high-temperature gas-cooled reactor (HTGR), has now been tested to full thermal power. Testing was conducted for the dual purposes of demonstrating component and system capability as a part of the rise-to-power program and determining core fluctuation/redistribution behavior under full power conditions. Both objectives were met. Full power performance of all major components and the achievement of nearly all design objectives has been verified. In addition, the tests showed that the fluctuation phenomenon has been corrected. Core region outlet temperature redistributions have been characterized, related to a physical mechanism, and shown to be inconsequential for overall plant operation

  13. Optimal Wind Power Uncertainty Intervals for Electricity Market Operation

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Ying; Zhou, Zhi; Botterud, Audun; Zhang, Kaifeng

    2018-01-01

    It is important to select an appropriate uncertainty level of the wind power forecast for power system scheduling and electricity market operation. Traditional methods hedge against a predefined level of wind power uncertainty, such as a specific confidence interval or uncertainty set, which leaves the questions of how to best select the appropriate uncertainty levels. To bridge this gap, this paper proposes a model to optimize the forecast uncertainty intervals of wind power for power system scheduling problems, with the aim of achieving the best trade-off between economics and reliability. Then we reformulate and linearize the models into a mixed integer linear programming (MILP) without strong assumptions on the shape of the probability distribution. In order to invest the impacts on cost, reliability, and prices in a electricity market, we apply the proposed model on a twosettlement electricity market based on a six-bus test system and on a power system representing the U.S. state of Illinois. The results show that the proposed method can not only help to balance the economics and reliability of the power system scheduling, but also help to stabilize the energy prices in electricity market operation.

  14. Summary of operating experience in Swiss nuclear power plants 1994

    International Nuclear Information System (INIS)

    1995-05-01

    In 1994 the Swiss nuclear power plants produced their highest-ever combined annual output. Their contribution to total electricity generation in the country was 36%. At Muehleberg the power uprate, undertaken in 1993, was effective for the first time for an entire year. The larger capacity of the new steam generators installed in 1993 in unit 1 of the Beznau NPP allows for an electric output of 103% of nominal power. The plant efficiency of the Goesgen and Leibstadt units was increased by replacing the low pressure turbines by the new ones with a modern design. The application for a power uprate of the Leibstadt reactor is still pending. For the first time in Switzerland, one of the reactor units, Beznau 2, operated on an extended cycle of one and a half years, with no refuelling outage in 1994. In spite of the replacements of two of its three low pressure turbines, Goesgen had the shortest refuelling shutdown since the start of commercial operation. The average number of reactor scrams at the Swiss plants remained stable, at less than one scram per reactor year. Re-inspection of crack indications detected in 1990 in the core shroud of the Muehleberg reactor revealed no significant changes. A crack indication was found in one of the other welds inspected. The Swiss government issued a limited operating licence for Beznau 2 for the next ten years, i.e. until the end of 2004. The only other unit with a limited operating licence (until 2003) is Muehleberg. The remaining three reactor units, have no time limits on their operating licences, in accordance with the Atomic Law. Goesgen is the first Swiss nuclear power plant having now produced more than 100 billion kWh. As from January 1, 1995, the nominal net power of the largest Swiss reactor unit, Leibstadt, has been fixed at 1030 MW; that of the Goesgen NPP has been increased by 25 MW to 965 MW. (author) figs., tabs

  15. Summary of operating experience in Swiss nuclear power plants 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    In 1994 the Swiss nuclear power plants produced their highest-ever combined annual output. Their contribution to total electricity generation in the country was 36%. At Muehleberg the power uprate, undertaken in 1993, was effective for the first time for an entire year. The larger capacity of the new steam generators installed in 1993 in unit 1 of the Beznau NPP allows for an electric output of 103% of nominal power. The plant efficiency of the Goesgen and Leibstadt units was increased by replacing the low pressure turbines by the new ones with a modern design. The application for a power uprate of the Leibstadt reactor is still pending. For the first time in Switzerland, one of the reactor units, Beznau 2, operated on an extended cycle of one and a half years, with no refuelling outage in 1994. In spite of the replacements of two of its three low pressure turbines, Goesgen had the shortest refuelling shutdown since the start of commercial operation. The average number of reactor scrams at the Swiss plants remained stable, at less than one scram per reactor year. Re-inspection of crack indications detected in 1990 in the core shroud of the Muehleberg reactor revealed no significant changes. A crack indication was found in one of the other welds inspected. The Swiss government issued a limited operating licence for Beznau 2 for the next ten years, i.e. until the end of 2004. The only other unit with a limited operating licence (until 2003) is Muehleberg. The remaining three reactor units, have no time limits on their operating licences, in accordance with the Atomic Law. Goesgen is the first Swiss nuclear power plant having now produced more than 100 billion kWh. As from January 1, 1995, the nominal net power of the largest Swiss reactor unit, Leibstadt, has been fixed at 1030 MW; that of the Goesgen NPP has been increased by 25 MW to 965 MW. (author) figs., tabs.

  16. Recent Operating Experience involving Power Electronics Failure in Korea Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Jaedo

    2015-01-01

    Recently, modern power electronics devices for electrical component were steadily increased in electrical systems which used for main power control and protection. To upgrade the system reliability we recommended the redundancy for electrical equipment trip system. The past several years, Korean Nuclear power plants have changed the electrical control and protection systems (Auto Voltage Regulator, Power Protection Relay) for main generator and main power protection relay systems. In this paper we deal with operating experience involving modern solid state power electronics failure in Korean nuclear power plants. One of the failures we will discuss the degraded phenomenon of power electronics device for CEDMCS(Control Element Drive Mechanism Control System). As the result of the failure we concerned about the modification for trip source of main generator excitation systems and others. We present an interesting issue for modern solid state devices (IGBT, Thyristors). (authors)

  17. Adequacy of operating reserves for power systems in future european wind power scenarios

    DEFF Research Database (Denmark)

    Das, Kaushik; Litong-Palima, Marisciel; Maule, Petr

    2015-01-01

    operating reserves. To study the effects of these imbalances, anticipated wind scenarios for European power systems are modelled for 2020 and 2030. Wind power forecasts for different time scales and real-time available wind power are modelled. Based on these studies, this paper qualitatively analyzes......Wind power generation is expected to increase in Europe by large extent in future. This will increase variability and uncertainty in power systems. Imbalances caused due to uncertainty in wind power forecast can trigger frequency instability in the system. These imbalances are handled using...... the adequacy of primary and secondary reserves requirements for future European power systems. This paper also discusses the challenges due to the uncertainty in wind power forecasts and their possible solutions for wind installation scenarios for 2020 and 2030....

  18. British Columbia Power Export Corporation: Operational review for operating year, October 1989 to September 1990

    International Nuclear Information System (INIS)

    1990-01-01

    The British Columbia Power Export Corporation (POWEREX) is a wholly owned subsidiary of British Columbia Hydro, established in 1988 as the single agency responsible for implementing the provincial policy of international electricity trade. POWEREX objectives are to conduct long term firm electricity trade utilizing private sector financing, operating capabilities, and generating sources. Short term electricity transactions are handled by the part of POWEREX called the Powerex Pool Operation. An operational review of POWEREX for 1989-90 is presented, giving information on export contracts, license approvals, export sales negotiations, pool operation revenues and sales, British Columbia Hydro generation and integrated system performance, and operational planning. 15 figs

  19. Measurement uncertainty recapture (MUR) power uprates operation at Kuosheng Nuclear Power Station

    International Nuclear Information System (INIS)

    Chang Chinjang; Wang Tunglu; Lin Chihpao

    2009-01-01

    Measurement Uncertainty Recapture PowerUprates (MUR PU) are achieved through the use of state-of-the-art feedwater flow measurement devices, i.e., ultrasonic flow meters (UFMs), that reduce the degree of uncertainty associated with feedwater flow measurement and in turn provide for a more accurate calculation of thermal power. The Institute of Nuclear Energy Research (INER) teamed with Sargent and Lundy, LLC (S and L), Pacific Engineers and Constructors, Ltd (PECL), and AREVA to develop a program and plan for the Kuosheng Nuclear Power Station (KNPS) MUR PU Engineering Service Project and for the assistance to Kuosheng MUR PU operation. After regulator's approval of the licensing requests, KSNPS conducted the power ascension test and switchover to the new rated thermal power for Unit 2 and Unit 1 on 7/7/2007 and 11/30/2007, respectively. From then on, KNPS became the first nuclear power plant implementing MUR PU operation in Taiwan and in Asia. (author)

  20. Power ramping/cycling experience and operational recommendations in KWU power plants

    International Nuclear Information System (INIS)

    Jan, R. von; Wunderlich, F.; Holzer, R.

    1980-01-01

    The power cycling and ramping experience of KWU is based on experiments in test and commercial reactors, and on evaluation of plant operation (PHWR, PWR and BWR). Power cycling of fuel rods have never lead to PCI failures. In ramping experiments, for fast ramps PCI failure thresholds of 480/420 W/cm are obtained at 12/23 GWd/t(U) burn-up for pressurized PWR fuel. No failures occurred during limited exceedance of the threshold with reduced ramp rate. Operational recommendations used by KWU are derived from experiments and plant experience. The effects of ramping considerations on plant operation is discussed. No rate restrictions are required for start-ups during an operating cycle or load follow operation within set limits for the distortion of the local power distribution. In a few situations, e.g. start-up after refueling, ramp rates of 1 to 5 %/h are recommended depending on plant and fuel design

  1. Expert system for operational personnel support during power unit operation control in regulation range

    International Nuclear Information System (INIS)

    Yanitskij, V.A.

    1992-01-01

    The problems met when developing the systems for NPP operator support in the process of power unit operation are considered. The expert system for NPP personnel intelligent support combining the properties belonging to the artificial intelligence systems including selection of the analysis method taking into account the concrete technological situation and capability of application of algothmic calculations of the equipment characteristics using the information accumulated during the system development, erection and operation is described

  2. Role of conceptual models in nuclear power plant operation

    International Nuclear Information System (INIS)

    Williams, M.D.; Moran, T.P.; Brown, J.S.

    1982-01-01

    A crucial objective in plant operation (and perhaps licensing) ought to be to explicitly train operators to develop, perhaps with computer aids, robust conceptual models of the plants they control. The question is whether we are actually able to develop robust conceptual models and validate their robustness. Cognitive science is just beginning to come to grips with this problem. This paper describes some of the evolving technology for building conceptual models of physical mechanisms and some of the implications of such models in the context of nuclear power plant operation

  3. Human-factor operating concept for Borssele Nuclear Power Station

    International Nuclear Information System (INIS)

    Wieman, J.L.

    1995-01-01

    The safety level in the operation of a reactor is determined basically by human beings. The Borssele Nuclear Power Station has carried out measures for improving the man-machine interface through training and operating instructions for the shift personnel. The retrofitting of control technology relevant to safety engineering should avoid operating instructions which can cause potential failures. A safety study has shown that the remaining risk following all retrofitting measures remains dependent to the extent of 80% on human factors and that human factors as a whole have a positive effect on reactor safety. (orig.) [de

  4. Feedback of operating experience in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The feedback of operating experience of nuclear facilities to the designers, manufacturers, operators and regulators is one important means of maintaining and improving safety. The Atomic Energy Control Board`s Advisory Committee on Nuclear Safety examined the means for feedback currently being employed, how effective they are and what improvements are advisable. The review found that the need for feedback of operating experience is well recognized within those institutions contributing to the safety of CANDU power reactors, and that the existing procedures are generally effective. Some recommendations, however, are submitted for improvement in the process.

  5. Feedback of operating experience in nuclear power plants

    International Nuclear Information System (INIS)

    1995-06-01

    The feedback of operating experience of nuclear facilities to the designers, manufacturers, operators and regulators is one important means of maintaining and improving safety. The Atomic Energy Control Board's Advisory Committee on Nuclear Safety examined the means for feedback currently being employed, how effective they are and what improvements are advisable. The review found that the need for feedback of operating experience is well recognized within those institutions contributing to the safety of CANDU power reactors, and that the existing procedures are generally effective. Some recommendations, however, are submitted for improvement in the process

  6. Application of reliability worth concepts in power system operational planning

    Energy Technology Data Exchange (ETDEWEB)

    Mello, J C.O. [Centro de Pesquisas de Energia Eletrica (CEPEL), Rio de Janeiro, RJ (Brazil); Silva, A.M. Leite da [Pontificia Univ. Catolica do Rio de Janeiro, RJ (Brazil); Pereira, M V.F. [Power System Research (PSR), Inc., Rio de Janeiro, RJ (Brazil)

    1994-12-31

    This work describes the application of a new methodology for calculating total system interruption costs in power system operational planning. Some important operational aspects are discussed: chronological load curves, customer damage functions for each consumer class, maintenance scheduling and non-exponential repair times. It is also presented the calculation of the probability distribution of the system interruption cost to improve the decision making process associated with alternative operational strategies. The Brazilian Southeastern system is used to illustrate all previous applications. (author) 24 refs., 8 figs., 4 tabs.

  7. U.S. Central Station Nuclear Power Plants: operating history

    International Nuclear Information System (INIS)

    1976-01-01

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

  8. Method of operation for a nuclear power plant

    International Nuclear Information System (INIS)

    Barleon, L.; Dalle Donne, M.; Dorner, S.

    1976-01-01

    A method for the operation of a nuclear power plant is described whose primary coolant circuit contains liquid metal as coolant, and for whose secondary circuit which is coupled to the first by means of heat exchangers, one or more chemical compositions dissociating at higher temperatures and recombining at lower temperatures or associating into the original types are used as operating medium. N 2 O 4 is suggested as operating medium, and metal halogenides e.g. Al 2 Cl 6 , Al 2 Br 6 are also cited as suitable. Corrosion dangers are regarded as low. (UWI) [de

  9. A Stochastic Operational Planning Model for Smart Power Systems

    Directory of Open Access Journals (Sweden)

    Sh. Jadid

    2014-12-01

    Full Text Available Smart Grids are result of utilizing novel technologies such as distributed energy resources, and communication technologies in power system to compensate some of its defects. Various power resources provide some benefits for operation domain however, power system operator should use a powerful methodology to manage them. Renewable resources and load add uncertainty to the problem. So, independent system operator should use a stochastic method to manage them. A Stochastic unit commitment is presented in this paper to schedule various power resources such as distributed generation units, conventional thermal generation units, wind and PV farms, and demand response resources. Demand response resources, interruptible loads, distributed generation units, and conventional thermal generation units are used to provide required reserve for compensating stochastic nature of various resources and loads. In the presented model, resources connected to distribution network can participate in wholesale market through aggregators. Moreover, a novel three-program model which can be used by aggregators is presented in this article. Loads and distributed generation can contract with aggregators by these programs. A three-bus test system and the IEEE RTS are used to illustrate usefulness of the presented model. The results show that ISO can manage the system effectively by using this model

  10. Internet applications in nuclear power plant operation management

    International Nuclear Information System (INIS)

    Munoz, M.

    2000-01-01

    The use of the Internet is quickly becoming widespread in practically all areas of business and industry. The nuclear industry should not remain indifferent to this new trend. This paper analyses some of the Internet applications that can be easily adapted to nuclear power plant operation management, including. (Author)

  11. Pilgrim Nuclear Power Station, Unit 1. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electric power generated in 1975 was 1,074,401 MW(e) with the generator on line 4,680.7 hrs. Information is presented concerning operations, maintenance, radioactive effluents and waste shipments, health physics, shutdowns, and personnel exposures

  12. Reliability assurance program for operational emergency ac power system

    International Nuclear Information System (INIS)

    Heineman, J.B.; Ragland, W.A.; Mueller, C.J.

    1985-01-01

    A comprehensive review of emergency ac power systems in nuclear generating plants (the vast majority of these plants contain redundant diesel generator systems) delineates several operational areas that can be improved by instituting a reliability assurance program (RAP), which initially upgrades the diesel generator performance and provides for ongoing monitoring and maintenance based upon alert levels

  13. Quality assurance during operation of a nuclear power plant

    International Nuclear Information System (INIS)

    Stolz, J.

    1980-01-01

    The lecture provides a description of the QA manual as operated in French nuclear power plants. Oral comments will include discussion of some difficulties in actual implementation. Also examples will be given of incidents in nuclear plants, which could have been mitigated or fully prevented by QA attitude. (orig./RW)

  14. 47 CFR 73.267 - Determining operating power.

    Science.gov (United States)

    2010-10-01

    ... may be checked by measuring the power at the transmitter terminals while either: (1) Operating the... the final amplifier stages have been modified pursuant to FCC approval, the licensee must furnish the FCC and also retain with the station records the measurement data used as a basis for determining the...

  15. Relativity evaluation of reliability on operation in nuclear power plant

    International Nuclear Information System (INIS)

    Inata, Takashi

    1987-01-01

    The report presents a quantitative method for evaluating the reliability of operations conducted in nuclear power plants. The quantitative reliability evaluation method is based on the 'detailed block diagram analysis (De-BDA)'. All units of a series of operations are separately displayed for each block and combined sequentially. Then, calculation is performed to evaluate the reliability. Basically, De-BDA calculation is made for pairs of operation labels, which are connected in parallel or in series at different subordination levels. The applicability of the De-BDA method is demonstrated by carrying out calculation for three model cases: operations in the event of malfunction of the control valve in the main water supply system for PWR, switching from an electrically-operated water supply pump to a turbin-operated water supply pump, and isolation and water removal operation for a low-pressure condensate pump. It is shown that the relative importance of each unit of a series of operations can be evaluated, making it possible to extract those units of greater importance, and that the priority among the factors which affect the reliability of operations can be determined. Results of the De-BDA calculation can serve to find important points to be considered in developing an operation manual, conducting education and training, and improving facilities. (Nogami, K.)

  16. Operation aid device upon periodical inspection of nuclear power plant

    International Nuclear Information System (INIS)

    Fukusaka, Ryoji.

    1997-01-01

    The present invention provides an operation aid device upon periodical inspection of a nuclear power plant, capable of controlling a plurality of control rods safely at good operation efficiency while maintaining subcritical state. Namely, a fuel exchange computer controls an operation for exchanging fuel assemblies upon periodical inspection. An operation aiding computer aids the exchanging operation of fuel assemblies. A control rod position monitoring device allows withdrawal of one control rod under the condition of establishment of entire control rod insertion signal upon operation of exchanging fuel assemblies. Whether all of the four fuel assemblies around one control rod have been entirely taken out or not is judged based on information on the fuel assembly exchanging operation. When conditions for the judgement for operation aiding computer are established, the all insertion signals for the entire control rods as the condition for the withdrawal of the control rods are bypassed, and operation enable signals for plurality control rods are outputted to a control rod manual operation device. (I.S.)

  17. Electric Vehicles for Improved Operation of Power Systems with High Wind Power Penetration

    OpenAIRE

    Larsen, Esben; Chandrashekhara, Divya K; Østergaard, Jacob

    2008-01-01

    In a power system with a high share of wind energy the wind fluctuation causes a variation in the power generation, which must be compensated from other sources. The situation in Denmark with a penetration of more than 20% wind in yearly average is presented. The introduction of electric drive vehicles (EDV) as flexible loads can improve the system operation. Bidirectional power exchange through batteries (vehicle to grid) can be seen as a storage system in the grid. An analysis of possible e...

  18. Summary of operating experience in Swiss nuclear power plants 1993

    International Nuclear Information System (INIS)

    1994-07-01

    In 1993 the Swiss nuclear power plants produced their third highest combined annual output. The contribution to the total electricity generation in the country was close to 37%. Replacement of the steam generators in Beznau Unit 1 resulted in a longer than usual annual outage. For the other four units the availability figures were close to, or exceeded, those of previous years. The energy utilization was, however, lowered due to load reduction in autumn resulting from unusually high production by the hydro-electric power plants. The steam generator replacement at Beznau enabled an increase in electrical power of about 2% without increase in reactor power. With the approval of the Swiss government in December 1992, the output of the Muehleberg power plant was increased in two stages by a total of 10%. The application for an unlimited operating license for Beznau Unit 2, and for a power uprate at the Leibstadt power plant, are still pending. The average number of scrams at the Swiss plants remained stable, at less than one scram per reactor year. As a result of experience in the Swedish nuclear power plant at Barsebaeck, the suction strainers of the emergency core cooling systems of the boiling water reactors at Muehleberg and Leibstadt were replaced by strainers with larger surface areas. The re-inspection of crack indications previously detected in the core shroud of the Muehleberg reactor and the penetration tubes in the reactor pressure vessel closure head of Beznau revealed no growth during the intervening operating periods. Following the completion of installation activities during the annual outages at Beznau Unit 1, Goesgen and Leibstadt, all Swiss nuclear power plants are now equipped with filtered containment venting systems. (author) figs., tabs

  19. Optimal Operation of Energy Storage in Power Transmission and Distribution

    Science.gov (United States)

    Akhavan Hejazi, Seyed Hossein

    In this thesis, we investigate optimal operation of energy storage units in power transmission and distribution grids. At transmission level, we investigate the problem where an investor-owned independently-operated energy storage system seeks to offer energy and ancillary services in the day-ahead and real-time markets. We specifically consider the case where a significant portion of the power generated in the grid is from renewable energy resources and there exists significant uncertainty in system operation. In this regard, we formulate a stochastic programming framework to choose optimal energy and reserve bids for the storage units that takes into account the fluctuating nature of the market prices due to the randomness in the renewable power generation availability. At distribution level, we develop a comprehensive data set to model various stochastic factors on power distribution networks, with focus on networks that have high penetration of electric vehicle charging load and distributed renewable generation. Furthermore, we develop a data-driven stochastic model for energy storage operation at distribution level, where the distribution of nodal voltage and line power flow are modelled as stochastic functions of the energy storage unit's charge and discharge schedules. In particular, we develop new closed-form stochastic models for such key operational parameters in the system. Our approach is analytical and allows formulating tractable optimization problems. Yet, it does not involve any restricting assumption on the distribution of random parameters, hence, it results in accurate modeling of uncertainties. By considering the specific characteristics of random variables, such as their statistical dependencies and often irregularly-shaped probability distributions, we propose a non-parametric chance-constrained optimization approach to operate and plan energy storage units in power distribution girds. In the proposed stochastic optimization, we consider

  20. Operating procedure automation to enhance safety of nuclear power plants

    International Nuclear Information System (INIS)

    Husseiny, A.A.; Sabri, Z.A.; Adams, S.K.; Rodriguez, R.J.; Packer, D.; Holmes, J.W.

    1989-01-01

    Use of logic statements and computer assist are explored as means for automation and improvement on design of operating procedures including those employed in abnormal and emergency situations. Operating procedures for downpower and loss of forced circulation are used for demonstration. Human-factors analysis is performed on generic emergency operating procedures for three strategies of control; manual, semi-automatic and automatic, using standard emergency operating procedures. Such preliminary analysis shows that automation of procedures is feasible provided that fault-tolerant software and hardware become available for design of the controllers. Recommendations are provided for tests to substantiate the promise of enhancement of plant safety. Adequate design of operating procedures through automation may alleviate several major operational problems of nuclear power plants. Also, automation of procedures is necessary for partial or overall automatic control of plants. Fully automatic operations are needed for space applications while supervised automation of land-based and offshore plants may become the thrust of new generation of nulcear power plants. (orig.)

  1. Safety of Nuclear Power Plants: Commissioning and Operation

    International Nuclear Information System (INIS)

    2011-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  2. Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  3. Safety of Nuclear Power Plants: Commissioning and Operation. Arabic Edition

    International Nuclear Information System (INIS)

    2011-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  4. Psychological characteristics of licensed nuclear power plant operators

    International Nuclear Information System (INIS)

    Sajwaj, T.; Ford, T.; McGee, R.K.

    1987-01-01

    The safe production of electricity by nuclear power plants has been the focus of considerable attention. Much of this concern has been focused on equipment and procedural issues, with less attention to the psychological factors that affect the operations staff of the plants, i.e., those individuals who are most directly responsible for a plant's operations. Stress and type A qualities would be significant for these individuals because of their relationships to job performance and health. Of equal significance would be work-related factors, such as job involvement and work pressure. Also of interest would be hostile tendencies because of the need for cooperation and communications among operations staff. Two variables could influence these psychological factors. One is the degree of responsibility for a plant's nuclear reactors. The individuals with the greatest responsibility are licensed by the US Nuclear Regulatory Commission (NRC). There are also individuals with less direct responsibilities who are not licensed. A second variable is the operating status of the plant, whether or not the plant is currently producing electricity. Relative to ensuring the safe operation of nuclear power plants, these data suggest a positive view of licensed operators. Of interest are the greater stress scores in the licensed staff of the operating plant in contrast with their peers in the nonoperating plant

  5. Safety of Nuclear Power Plants: Commissioning and Operation (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  6. Operation of Modern Distribution Power Systems in Competitive Electricity Markets

    DEFF Research Database (Denmark)

    Hu, Weihao

    , DG units, loads and electricity price are studied. Further, the effect of energy storage systems will be considered, and an optimal operation strategy for energy storage devices in a large scale wind power system in the electricity market is proposed. The western Danish power system, which has large...... strategy for trading wind power in the Danish short-term electricity market in order to minimize the imbalance costs for regulation. A load optimization method based on spot price for demand side management in Denmark is proposed in order to save the energy costs for 3 types of typical Danish consumers...... maximum profit of the BESS is proposed. Two kinds of BESS, based on polysulfide-bromine (PSB) and vanadium redox (VRB) battery technologies, are studied. Optimal operation strategies of PEV in the spot market are then proposed in order to decrease the energy cost for PEV owners. Furthermore...

  7. Meteorological safeguarding of nuclear power plant operation in Czechoslovakia

    International Nuclear Information System (INIS)

    Rak, J.; Skulec, S.

    1976-01-01

    A meteorological tower 200 m high has to be built for meteorological control of the operation of the A-1 nuclear power plant at Jaslovske Bohunice. This meteorological station will measure the physical properties of the lower layers of the atmosphere, carry out experimental verifications of the models of air pollution, investigate the effects of waste heat and waste water from the nuclear power plant on the microclimate, provide the theoretical processing of measured data with the aim of selecting the most favourable model for conditions prevailing in the Czechoslovak Socialist Republic, perform basic research of the physical properties of the ground and boundary layers of the atmosphere and the coordination of state-wide plans in the field of securing the operation of nuclear power plants with regard to meteorology. (Z.M.)

  8. A methodology for nuclear power plant operational events evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jeferson, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CGRC/CNEN), Rio de janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo de Combustivel; Costa, Sergio Dias, E-mail: sergiodiascosta@hotmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Operational events are normal occurrences in industrial plants and in nuclear power plants. The evaluation of operational events gains importance when it comes specifically to nuclear power plants due to the proportions that the impact and the consequences of these events may cause to the installation itself, their workers, the external area of the nuclear installation, the environment and to the public in general. These consequences, for the operation of these facilities can range from very little, until the consequences that lead to accidents and can cause significant impacts. Operational events may be associated or have influence in many fields of knowledge, such as operation, maintenance, engineering, Radiological Protection, physical protection, chemistry, Human or Organizational Factors and external events, among others. The accident at the Fukushima Daichi nuclear power plant, shows the importance of exhausting all the studies concerning operational events in order to improve the operational safety of nuclear plants, considering all the causes and possible consequences. In this context, the evaluation of operational events discipline emerges as an important and relevant tool to contribute to the maintenance and/or improvement of the operational safety of nuclear installations. Not without reason the nuclear industry actively participates in programs of exchange of operational experience, where relevant events are thoroughly evaluated and discussed in specific forums, such as power plant operators, regulators and/or joint technical meetings, always with the purpose to prevent, minimize or mitigate its consequences. Any evaluation of operational events passes necessarily by an in-depth study of the circumstances of the event, culminating with the identification of your cause and proposition of corrective actions to prevent recurrence of similar events. Additionally, the events should not be studied individually, but evaluated within a temporal context in order

  9. A methodology for nuclear power plant operational events evaluation

    International Nuclear Information System (INIS)

    Araujo, Jeferson

    2015-01-01

    Operational events are normal occurrences in industrial plants and in nuclear power plants. The evaluation of operational events gains importance when it comes specifically to nuclear power plants due to the proportions that the impact and the consequences of these events may cause to the installation itself, their workers, the external area of the nuclear installation, the environment and to the public in general. These consequences, for the operation of these facilities can range from very little, until the consequences that lead to accidents and can cause significant impacts. Operational events may be associated or have influence in many fields of knowledge, such as operation, maintenance, engineering, Radiological Protection, physical protection, chemistry, Human or Organizational Factors and external events, among others. The accident at the Fukushima Daichi nuclear power plant, shows the importance of exhausting all the studies concerning operational events in order to improve the operational safety of nuclear plants, considering all the causes and possible consequences. In this context, the evaluation of operational events discipline emerges as an important and relevant tool to contribute to the maintenance and/or improvement of the operational safety of nuclear installations. Not without reason the nuclear industry actively participates in programs of exchange of operational experience, where relevant events are thoroughly evaluated and discussed in specific forums, such as power plant operators, regulators and/or joint technical meetings, always with the purpose to prevent, minimize or mitigate its consequences. Any evaluation of operational events passes necessarily by an in-depth study of the circumstances of the event, culminating with the identification of your cause and proposition of corrective actions to prevent recurrence of similar events. Additionally, the events should not be studied individually, but evaluated within a temporal context in order

  10. Safety of Nuclear Power Plants: Commissioning and Operation

    International Nuclear Information System (INIS)

    2011-01-01

    The safety of a nuclear power plant is ensured by means of proper site selection, design, construction and commissioning, and the evaluation of these, followed by proper management, operation and maintenance of the plant. In a later phase, a proper transition to decommissioning is required. The organization and management of plant operations ensures that a high level of safety is achieved through the effective management and control of operational activities. This publication is a revision of the Safety Requirements publication Safety of Nuclear Power Plants: Operation, which was issued in 2000 as IAEA Safety Standards Series No. NS-R-2. The purpose of this revision was to restructure Safety Standards Series No. NS-R-2 in the light of new operating experience and new trends in the nuclear industry; to introduce new requirements that were not included in Safety Standards Series No. NS-R-2 on the operation of nuclear power plants; and to reflect current practices, new concepts and technical developments. This update also reflects feedback on the use of the standards, both from Member States and from the IAEA's safety related activities. The publication is presented in the new format for Safety Requirements publications. The present publication reflects the safety principles of the Fundamental Safety Principles. It has been harmonized with IAEA Safety Standards Series No. GS-R-3 on The Management System for Facilities and Activities. Guidance on the fulfilment of the safety requirements is provided in supporting Safety Guides. The terminology used in this publication is defined and explained in the IAEA Safety Glossary. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This

  11. A subleading power operator basis for the scalar quark current

    Science.gov (United States)

    Chang, Cyuan-Han; Stewart, Iain W.; Vita, Gherardo

    2018-04-01

    Factorization theorems play a crucial role in our understanding of the strong interaction. For collider processes they are typically formulated at leading power and much less is known about power corrections in the λ ≪ 1 expansion. Here we present a complete basis of power suppressed operators for a scalar quark current at O({λ}^2) in the amplitude level power expansion in the Soft Collinear Effective Theory, demonstrating that helicity selection rules significantly simplify the construction. This basis applies for the production of any color singlet scalar in q\\overline{q} annihilation (such as b\\overline{b}\\to H ). We also classify all operators which contribute to the cross section at O({λ}^2) and perform matching calculations to determine their tree level Wilson coefficients. These results can be exploited to study power corrections in both resummed and fixed order perturbation theory, and for analyzing the factorization properties of gauge theory amplitudes and cross sections at subleading power.

  12. HEMP emergency planning and operating procedures for electric power systems

    Energy Technology Data Exchange (ETDEWEB)

    Reddoch, T.W.; Markel, L.C. (Electrotek Concepts, Inc., Knoxville, TN (United States))

    1991-01-01

    Investigations of the impact of high-altitude electromagnetic pulse (HEMP) on electric power systems and electrical equipment have revealed that HEMP creates both misoperation and failures. These events result from both the early time E[sub 1] (steep-front pulse) component and the late time E[sub 3] (geomagnetic perturbations) component of HEMP. In this report a HEMP event is viewed in terms of its marginal impact over classical power system disturbances by considering the unique properties and consequences of HEMP. This report focuses on system-wide electrical component failures and their potential consequences from HEMP. In particular, the effectiveness of planning and operating procedures for electric systems is evaluated while under the influence of HEMP. This assessment relies on published data and characterizes utilities using the North American Electric Reliability Council's regions and guidelines to model electric power system planning and operations. Key issues addressed by the report include how electric power systems are affected by HEMP and what actions electric utilities can initiate to reduce the consequences of HEMP. The report also reviews the salient features of earlier HEMP studies and projects, examines technology trends in the electric power industry which are affected by HEMP, characterizes the vulnerability of power systems to HEMP, and explores the capability of electric systems to recover from a HEMP event.

  13. Application of bounding spectra to seismic design of piping based on the performance of above ground piping in power plants subjected to strong motion earthquakes

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1995-02-01

    This report extends the potential application of Bounding Spectra evaluation procedures, developed as part of the A-46 Unresolved Safety Issue applicable to seismic verification of in-situ electrical and mechanical equipment, to in-situ safety related piping in nuclear power plants. The report presents a summary of earthquake experience data which define the behavior of typical U.S. power plant piping subject to strong motion earthquakes. The report defines those piping system caveats which would assure the seismic adequacy of the piping systems which meet those caveats and whose seismic demand are within the bounding spectra input. Based on the observed behavior of piping in strong motion earthquakes, the report describes the capabilities of the piping system to carry seismic loads as a function of the type of connection (i.e. threaded versus welded). This report also discusses in some detail the basic causes and mechanisms for earthquake damages and failures to power plant piping systems

  14. Leakage characterization of a piloted power operated relief valve

    International Nuclear Information System (INIS)

    Ezekoye, L.I.; Hess, M.D.

    1995-01-01

    In Westinghouse Pressurized Water Reactors (PWRs), power operated relief valves (PORVs) are used to provide overpressure protection of the Pressurizer. The valves are fail closed globe valves which means that power is required to open the valves and, on loss of power, the valves close. There are two ways to operate the PORVs. The more common way is to directly couple the disc to an actuator via a disc-stem assembly. The type of design is not the object of this paper. The other and less common way of operating a PORV is by piloting the main valve such that the opening or closing of a pilot valve opens and closes the main valve. This is the design of interest. In most plants, the PORVs are installed with a water loop seal while in some plants no water loop seals are used. It is generally accepted that loop seal installation minimizes valve seat leakage. In non-loop seal installation, the valve seat is exposed to steam which increases the potential for seat leakage. This paper describes the results of some tests performed with nitrogen and steam to characterize the leakage potential of a pilot operated PORV. The test results were compared with seat leakage tests of check valves to provide insight on the leakage testing of pilot operated valves and check valves. The paper also compares the test data with leakage estimates using the ASME/ANSI OM Code guidance on valve leakage

  15. Quality management for nuclear power plant operation: A manual

    International Nuclear Information System (INIS)

    1990-01-01

    The experience from well operated nuclear power plants shows that achievement of safe, reliable and economic performance is closely related to a strong commitment and involvement by the management personnel. A system of controls is necessary to ensure that satisfactory quality in operation is achieved and maintained over the long term. The key to achieving and assuring quality lies in the ability of management to define performance objectives and to ensure that significant safety and reliability problems are prevented or detected early and resolved. This Manual has been developed by the IAEA to assist plant managers in fulfilling their responsibility with regard to the control and direction of quality and of quality assurance activities in nuclear power plant operation. It emphasizes quality objectives for nuclear power plant operation and indicates the way in which a quality system based on quality assurance principles as established in the IAEA NUSS documents can be used by managers to accomplish these objectives. Since the Manual is mainly directed at management personnel, it is presented in the form of short highlighted practices complemented by typical examples of forms and procedures. Since not all the activities under the heading of quality in operation could be covered in a single document, the activities selected for this Manual comprise those where it was felt that practical advice is generally needed. A pragmatic document useful for direct application by plant managers was the envisaged objective

  16. The evaluation of operator reliability factors on power reactor

    International Nuclear Information System (INIS)

    Karlina, Itjeu; Supriatna, Piping; W, Suharyo; Santosa, Kussigit; Darlis; S, Bambang; Y, Sasongko

    1999-01-01

    The sophisticated technology system was not assured the reliability system itself because it has contained a part of human dependence affected successfully of reactor operation either how work smoothly and safe or failure ac cured and then accident appears promptly. The evaluation of operator reliability factor on ABWR power reactor has been carried out which consist of criterion skill and workload according to NUREG/CR-2254, NUREG/CR-4016 and NUREG-0835 the reactor operation reliability emphasize to the operator are synergic between skill and workload themselves. The employee's skill will affect to the type and level of their tasks. The operator's skill depend on education and experiences, position or responsibility of tasks, physical conditions (age uninvalid of physic/mental

  17. 14 CFR 101.25 - Operating limitations for Class 2-High Power Rockets and Class 3-Advanced High Power Rockets.

    Science.gov (United States)

    2010-01-01

    ... Power Rockets and Class 3-Advanced High Power Rockets. 101.25 Section 101.25 Aeronautics and Space... OPERATING RULES MOORED BALLOONS, KITES, AMATEUR ROCKETS AND UNMANNED FREE BALLOONS Amateur Rockets § 101.25 Operating limitations for Class 2-High Power Rockets and Class 3-Advanced High Power Rockets. When operating...

  18. Gas-fired power plants: Investment timing, operating flexibility and CO2 capture

    International Nuclear Information System (INIS)

    Fleten, Stein-Erik; Naesaekkaelae, Erkka

    2010-01-01

    We analyze investments in gas-fired power plants based on stochastic electricity and natural gas prices. A simple but realistic two-factor model is used for price processes, enabling analysis of the value of operating flexibility, the opportunity to abandon the capital equipment, as well as finding thresholds for energy prices for which it is optimal to enter into the investment. We develop a method to compute upper and lower bounds on plant values and investment threshold levels. Our case study uses representative power plant investment and operations data, and historical forward prices from well-functioning energy markets. We find that when the decision to build is considered, the abandonment option does not have significant value, whereas the operating flexibility and time-to-build option have significant effect on the building threshold. Furthermore, the joint value of the operating flexibility and the abandonment option is much smaller than the sum of their separate values, because both are options to shut down. The effects of emission costs on the value of installing CO 2 capture technology are also analyzed.

  19. Hydrogen-powered lawn mower: 14 years of operation

    International Nuclear Information System (INIS)

    Yvon, K.; Lorenzoni, J.-L.

    2006-01-01

    Our hydrogen-powered lawn mower [Yvon K, Lorenzoni J-L. Hydrogen powered lawn mower. Int J Hydrogen Energy 1993; 18, 345-48] has been operated without major interruption during the past 14 years. The commercial model was originally running on gasoline and was adapted to hydrogen by making small adjustments to the carburettor and by installing a hydrogen reservoir containing solid-state metal hydrides. During the evaluation period the only maintenance work was changing the lubricating oil of the engine once a year, and reactivating the metal hydride powder by external heating after an accidental inlet of air into the reservoir. There occurred no technical failure, and there was no safety incident, neither during operation nor during recharging of hydrogen. This demonstrates that a hydrogen-operated device of this type is mature for use by greater public. Cost and marketing issues are discussed. (author)

  20. Institute of Nuclear Power Operations annual report, 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen's joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO's 1993 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  1. Institute of Nuclear Power Operations 1994 annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  2. Institute of Nuclear Power Operations 1994 annual report

    International Nuclear Information System (INIS)

    1994-01-01

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen's joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO's 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  3. Power consumption analysis of operating systems for wireless sensor networks.

    Science.gov (United States)

    Lajara, Rafael; Pelegrí-Sebastiá, José; Perez Solano, Juan J

    2010-01-01

    In this paper four wireless sensor network operating systems are compared in terms of power consumption. The analysis takes into account the most common operating systems--TinyOS v1.0, TinyOS v2.0, Mantis and Contiki--running on Tmote Sky and MICAz devices. With the objective of ensuring a fair evaluation, a benchmark composed of four applications has been developed, covering the most typical tasks that a Wireless Sensor Network performs. The results show the instant and average current consumption of the devices during the execution of these applications. The experimental measurements provide a good insight into the power mode in which the device components are running at every moment, and they can be used to compare the performance of different operating systems executing the same tasks.

  4. Load following operation of nuclear power plants for meeting power system requirements

    International Nuclear Information System (INIS)

    Isoda, Hachiro

    1987-01-01

    This paper describes a calculating program on the availability factors of nuclear, thermal and pumed storage hydro power stations and some calculated results for typical three load factors, 55 %, 60 % and 71 %, are provided when the share of the nuclea power station in the generation facilities is increased. The load following requirement of the nuclear power station is also provided. Load following requirement: If there is a 10 % pumped storage hydro power station, the nuclear power station enables to be operated with its rated output up to 30 % - 35 % of its share. Its daily load following operation for 40 % and 50 % nuclear power station needs every weekend and every day respectively. Availability factor: The availability factor of the nuclear power station manages to get 80 % (maximum availability factor of the nuclear power station in this study) up to 30 % share of it with 10 % pumpued storage hydro power station. When the nuclear power station shares 40 % and 50 %, its availability factor decreases down 1 % and 5 % respectively. (author)

  5. Management of nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    Kueffer, K.

    1980-01-01

    This lecture covers management aspects which have an immediate bearing on safety and identifies the objectives and tasks of management which are required for safe operation of a nuclear power plant and is based on the Codes of Practice and Safety Guides of the IAEA as well as arrangements in use at the Swiss Nuclear Power Station Beznau. This lecture - discusses the factors to be considered in structuring the operating organization, the support to be provided to plant management, the services and facilities needed and the management system for assuring the safety tasks are performed - describes the responsibilities of plant management and operating organization - outlines the requirements for recruitment, training and retraining as well as qualification and authorization of personnel - describes the programmes for maintenance, testing, examination, inspection, radiological protection, quality assurance, waste management, fuel management, emergency arrangement and security - describes the development of plant operating procedures including procedures to protect the personnel - outlines the requirements for initial and subsequent operation - describes the importance for evaluation and feedback of operating experience - describes the procedures for changes in hardware, procedures and set points - outlines the information flow and the requirements in reference to records and reports. (orig./RW)

  6. The safety approach in the operation of EDF power plants

    International Nuclear Information System (INIS)

    Bertron, L.; Mira, J.J.

    1988-01-01

    To get a view on what is involved in maintaining a high level of safety in the operation of EdF nuclear power plants, it may be recalled that in 1987, 76 % of the EdF production was nuclear. The nuclear plants include thirty-four standard PWR 900 plants, fourteen PWR 1300 plants, the 305 MW SENA PWR, the four 500 MW GCR: CHINON A3 plant, St-LAURENT A1 (390 MW), A2 (450 MW) and BUGEY 1 (540 MW), the 233 MW PHENIX fast breeder reactor and the CREYS-MALVILLE 1200 MW fast breeder reactor, now being prepared for a new startup after the 1987 incident. So the importance of a safe operation of this investment is considerable for EdF, which is the designer, owner, industrial architect and operator. According to the French regulations, EdF is responsible for the safe operation of its power plants. A considerable human component is also at stake, as the safe operation of plants implies all the personnel to varying degrees. There are 15,000 such employees, all of whom have to be trained, competent and motivated. The operation of this system for 340 reactor-years has to-date resulted in no incident of any significant impact on the environment. Right from the start, safety in operation has always been an essential and clearly stated priority. Among other lessons the Three-Mile Island and Chernobyl accidents have reinforced the conviction that the human factors, the man-machine interface, and the safety culture were determining elements. With forty-eigh PWR plants in service, the problem is to maintain safe operation of a system now running at cruising speed, but also including some units (particularly the GCRs) that must be prepared for decommissioning. In addition EDF has to demonstrate the safe operations of CREYS MALVILLE, fast breeder reactor

  7. Effects of delaying the operation of a nuclear power plant

    International Nuclear Information System (INIS)

    Hill, L.J.; Rainey, J.A.; Tepel, R.C.; Van Dyke, J.W.

    1983-12-01

    This report documents a study of an actual 24-month nuclear power plant licensing delay. A representative utility was chosen for examination. The research was oriented toward determination of the licensing delay's impact on the utility's operating results, ratepayers, and security issues. The methodology utilized to estimate those impacts involved the recursive interaction of a generation costing program to estimate replacement fuel costs and a financial regulatory model to concomitantly determine the impact on the utility, its ratepayers and security issues. The latter model was executed under six alternate scenarios: (1) no delay in the plant's operation; (2) a 24-month delay; (3) a 24-month delay but further assuming all replacement power was generated by coal-fired plants; (4) a 24-month delay assuming all replacement power from oil-fired plants; (5) no delay but assuming the capital cost of the plant was twice as large; and (6) a 24-month delay with the capital cost of the plant twice as large. Three primary conclusions were made. First, under all scenarios, a 24-month delay in operation of the plant has an adverse impact on the utility's internal generation of funds. Second, although electricity rates are not appreciably affected by the delay, the direction of electricity price changes is contingent on the source of fuel used for replacement power. Finally, a 24-month delay has an adverse impact on the indicators used to evaluate the financial soundness of the utility in all cases under consideration

  8. Information needs in nuclear power plants during low power operation modes

    Energy Technology Data Exchange (ETDEWEB)

    Tommila, Teemu; Fantoni, Paolo F.; Zander, Ralf M.

    1998-02-01

    During the past few years an increasing attention has been paid to the safety of shutdown and refuelling operations. It has turned out that the risks during shutdown may be comparable to the risks of power operation. The goal of this report is to identify information requirements related to low power operating modes of nuclear power plants. These include, for example, warm and cold shutdowns, refuelling and maintenance, as well as related state transitions such as start-up and shut-down. The focus of the report is on planned refuelling outages and the role of the control room in managing the outage activities. As a starting point, the basic terminology and characteristics of low power operation are discussed. The current situation at nuclear power plants and some recent developments in information technology are reviewed. End-users' requirements and enabling technologies are combined in order to identify the opportunities for new information technology tools in low power operation. The required features of process control systems and maintenance information systems are described. Common plant modelling techniques, open software architectures and functional structuring of the process control system are suggested to be the key issues in the long-term development of operator support systems. On a shorter time scale, new tools solving limited practical problems should be developed and evaluated. This would provide a basis for the features needed for low power operation, including for example, outage planning, on-line risk monitoring, management of outage tasks, adaptive alarm handling, computerised procedures and task-oriented human interfaces. (author)

  9. Using management of aging in German nuclear power plants - aspects of KTA 1403 pertaining to residual power operation, post-shutdown operation and residual operation

    International Nuclear Information System (INIS)

    Barreiro, Pablo; Bever, Thomas; Brast, Gerhard; Elsche, Bjoern; Reese, Sven H.; Grossmann, Patrick; Widera, Martin; Huettner, Frank; Linnemann, Thomas; Smit, Swen-Olaf; Zander, Ralf-Michael

    2013-01-01

    Management of aging in nuclear power plants originated in the United States of America and became a topic of debate in Germany from the late 1990s onward. On the basis of the existing plant-specific measures practiced comprehensively, KTA 1403, ''Management of Aging in Nuclear Power Plants'', was drafted and finalized in 2010. This publication first presents the context of AM with regard to German nuclear power plants, including references to national and international historical developments. Against this backdrop, the difference between management of aging and lifetime management is discussed next. This is followed by a description of the status of the AM process in nuclear power plants currently in operation, especially organizational plant-specific implementation. As a consequence of the decision by the German federal government to discontinue the peaceful use of nuclear power in Germany and the associated 13th amendment to the Atomic Energy Act of July 31, 2011, a considerable part of the German nuclear power plant park already lost its right of power operation. In this situation, aspects of AM are discussed for plants in the no-power, post-operation and residual operation phases. Finally, experience accumulated in plant-specific execution of the AM process on the basis of KTA 1403 is considered and summarized.

  10. Nuclear power plants after Angra-3. Property and operation flexibility

    International Nuclear Information System (INIS)

    Deppe, Lothario

    2008-01-01

    The present work analyses the consequences that will be introduced with the modifications in the actual existing systematic related to the property and operation of nuclear power plants, coming from the legislation of 2004 that establishes that the electric energy distribution concessionaires acquire energy for attending its markets through bid in the modality of auction conducted by ANEEL - Brazilian Agency of Electric Energy. This systematic means that probably the Nuclear Power Plants after Angra-3 will be submitted to this auction process. The present report analyses all these questions and proposes solutions that seems to be the most obvious and viable

  11. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    International Nuclear Information System (INIS)

    1995-06-01

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience

  12. Non-Power Reactor Operator Licensing Examiner Standards

    International Nuclear Information System (INIS)

    1994-06-01

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR Part 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, this standard will be revised periodically to accommodate comments and reflect new information or experience

  13. The Chooz power station: ten years of operation

    International Nuclear Information System (INIS)

    Teste du Bailler, Andre

    1977-01-01

    The switching into actual service of the Chooz plant, the first pressurized water reactor ever built in France, occurred on 3rd april 1967. Ten years later, one can establish a highly positive balance schedule of plant's operation whose availability is satisfactory, except the mechanical failure which occurred during the startup. The behavior of the equipment, in particular of the components of the primary loop, was satisfactory in its whole since it allowed the gradual increase in capacity by 15% with respect to the initial design. It allowed also the achievment of noticeable progress in the design of equipment intended for the new power stations. Interesting results have also been obtained in radioprotection, working conditions of the staff and environment protection fields. Finally, the training of the operating teams has been closely followed, whether it concerned the operators directly affected by plant operation or the trainees gathered in a school specially organized for this purpose and transferred since to a training Center [fr

  14. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience.

  15. BR3/Vulcain Nuclear Power Station. Construction and Operational Experience

    Energy Technology Data Exchange (ETDEWEB)

    Storrer, J. [Belgonucleaire, S.A., Brussels (Belgium)

    1968-04-15

    A full-scale reactor experiment was set out as the main objective of the Vulcain research and development programme agreed in May 1962 between the UKAEA and BelgoNucleaire, manager of ''Syndicat Vulcain''. Vulcain uses variable moderation as the long-term method to control reactivity: the reactor is cooled and moderated by a mixture of heavy and light water, the D{sub 2}O content being stepwise reduced to permit power operation with all control rods completely out of the core. To carry out the Vulcain power experiment it was decided to modify the BR3 nuclear power plant located at Mol, Belgium, which had operated from 1962 to 1964 as a conventional PWR with outputs of 40.9 MW(th) and 11.45 MW(e). The BR3/Vulcain plant was started in December 1966 and since then is running with a load factor around 90%. It is the first time that such a reactor type has been built and operated and the experience gained by its design, construction, commissioning and operation has proven to be most valuable. D{sub 2}O is being used at a pressure (2000 lb/in{sup 2} abs.) never before achieved in a heavy-water reactor and the leak rate from the HP primary systems to the atmosphere has been kept to a negligible value, around 1 to 2 grams/h. Commissioning of the primary plant had been carried out with light water first without fuel, and thereafter with fuel, at which time the water was poisoned with boric acid. The reactor vessel contains experimental devices such as 65 in-pile instrumentation detectors and four hydraulically operated Zircaloy control rods. They required the interposition of a collar between the vessel and its lid. Refuelling is performed under boronated light water, the interchange between the primary water and the H{sub 2}O being carried out by means of a draining and spraying system. The reactor had been operated for two years before its modifications for Vulcain: many lessons have therefore been learned about working on irradiated systems. The BR3/Vulcain core has a

  16. Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

  17. Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2000-01-01

    This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

  18. It's done... or the unmanned operation in hydro power plants

    International Nuclear Information System (INIS)

    Chudy, M.

    2009-01-01

    Looking back at the two years of activities performed while launching the individual Hydro Power Plants (HPP) of the Slovenske elektrarne, a.s. into the unmanned operation, there was 'quantum' of work done during the implementation of each new HPP in the area of group output regulation, substation management, failure and alarm record and evaluation system, technological and information service. It is a good feeling to see the results of the work - when it works. Someone could say that we just test the project at one HPP and the others just get implemented. The fact that the HPPs differ from each other brings its specifics, which needed to be handled individually in the SW or HW area, or in terms of communication. We should definitely mention the enthusiasm and helpfulness of the employees even at the cost of their free time spent in launching the power plants into unmanned operation. The reward for the hours spent dealing with the technical issues and revealing the shortcomings in the whole operation management process is today in the greater possibilities of gaining an overviews of the events in the operation of each HPP or TG generation unit. However, our hands are little less free to perform interventions in the control systems - time for the maintenance - necessary planning of the outages - coordination within the operation preparation. (author)

  19. European Clearinghouse for Nuclear Power Plants Operational Experience Feedback

    International Nuclear Information System (INIS)

    Martin Ramos, M.; Noel, M.

    2010-01-01

    In the European Union, in order to support the Community activities on operational experience, a centralized regional network on nuclear power plants operational experience feedback (European Clearinghouse on Operational Experience Feedback for Nuclear Power Plants) was established in 2008 at the EC JRC-IE, Petten (The Netherlands) on request of nuclear Safety Authorities of several Member States. Its main goal is to improve the communication and information sharing on OEF, to promote regional collaboration on analyses of operational experience and dissemination of the lessons learned. The enlarged EU Clearinghouse was launched in April 2010, and it is currently gathering the Regulatory Authorities of Finland, Hungary, Lithuania, the Netherlands, Romania, Slovenia, Switzerland, Bulgaria, Czec Republic, France, Germany, Slovak Republic, and Spain (these last six countries as observers). The OECD Nuclear Energy Agency, the IAEA, the EC Directorates General of the JRC and ENER are also part of the network. Recently, collaboration between some European Technical Support Organizations (such IRSN and GRS) and the EU Clearinghouse has been initiated. This paper explains in detail the objectives and organization of the EU Clearinghouse, as well as the most relevant activities carried out, like research work in trend analysis of events ocurred in NPP, topical reports on particular events, dissemination of the results, quarterly reports on events reported publicly and operational experience support to the members of the EU Clearinghouse. (Author)

  20. Procedure for following external nuclear power plant operating experience

    International Nuclear Information System (INIS)

    Kostadinov, V.

    2003-01-01

    Slovenian Nuclear Safety Administration (SNSA) has developed computer database and the procedure for following-up and investigating external nuclear operating experience and administrative requirements. The SNSA's primary goal is to investigate safety significant events in due time, to analyze them from the regulatory point of view and to ensure that meaningful lessons be learned and used for improvement of the safe operation of Slovenian Nuclear Power Plant Krsko. Moreover, we intend to make uniform format and method for reporting broader spectrum of events analyzed including low level event reporting. (author)

  1. Analysis of operating experience of nuclear power plants

    International Nuclear Information System (INIS)

    Volta, G.; Amesz, J.; Mancini, G.

    1981-01-01

    The power reactors operating experience has been matter for studies at the Joint Research Centre of the C.E.C. with the aim of validating probabilistic analysis models and of setting up data banks concerning reliability, availability of components and systems and safety related events. The report shows problems encountered and solutions given to attain the goal. For what concerns validation, the need of more satisfactory models that could handle both the technical and the organizational aspects of an operating plant is shown. For what concerns the data banks the possibilities opened by a coherent international system of classification are underlined. (author)

  2. Simplified reactive power management strategy for complex power grids under stochastic operation and incomplete information

    International Nuclear Information System (INIS)

    Vlachogiannis, John G.

    2009-01-01

    In the current released energy market, the large-scale complex transmission networks and the distribution ones with dispersed energy sources and 'intelligent' components operate under uncertainties, stochastic and prior incomplete information. A safe and reliable operation of such complex power grids is a major issue for system operators. Under these circumstances an online reactive power management strategy with minimum risk concerning all uncertain and stochastic parameters is proposed. Therefore, new concepts such as reactive power-weighted node-to-node linking and reactive power control capability are introduced. A distributed and interconnected stochastic learning automata system is implemented to manage, in a unified and unique way, the reactive power in complex power grids with stochastic reactive power demand and detect the vulnerable part. The proposed simplified strategy can also consider more stochastic aspects such as variable grid's topology. Results of the proposed strategy obtained on the networks of IEEE 30-bus and IEEE 118-bus systems demonstrate the effectiveness of the proposed strategy.

  3. Thunderstorm Algorithm for Determining Unit Commitment in Power System Operation

    Directory of Open Access Journals (Sweden)

    Arif Nur Afandi

    2016-12-01

    Full Text Available Solving the unit commitment problem is an important task in power system operation for deciding a balanced power production between various types of generating units under technical constraints and environmental limitations. This paper presents a new intelligent computation method, called the Thunderstorm Algorithm (TA, for searching the optimal solution of the integrated economic and emission dispatch (IEED problem as the operational assessment for determining unit commitment. A simulation using the IEEE-62 bus system showed that TA has smooth convergence and is applicable for solving the IEED problem. The IEED’s solution is associated with the total fuel consumption and pollutant emission. The proposed TA method seems to be a viable new approach for finding the optimal solution of the IEED problem.

  4. Security assessment for intentional island operation in modern power system

    DEFF Research Database (Denmark)

    Chen, Yu; Xu, Zhao; Østergaard, Jacob

    2011-01-01

    be increased. However, when to island or how to ensure the islanded systems can survive the islanding transition is uncertain. This article proposes an Islanding Security Region (ISR) concept to provide security assessment of island operation. By comparing the system operating state with the ISR, the system......There has been a high penetration level of Distributed Generations (DGs) in distribution systems in Denmark. Even more DGs are expected to be installed in the coming years. With that, to utilize them in maintaining the security of power supply is of great concern for Danish utilities. During...... the emergency in the power system, some distribution networks may be intentionally separated from the main grid to avoid complete system collapse. If DGs in those networks could continuously run instead of immediately being shut down, the blackout could be avoided and the reliability of supply could...

  5. Thermal impact assessment of multi power plant operations on estuaries

    International Nuclear Information System (INIS)

    Eraslan, A.H.; Kim, K.H.; Harris, J.L.

    1977-01-01

    The assessment of the thermal impact of multi power plant operations on large estuaries requires careful consideration of the problems associated with: re-entrainment, re-circulation, thermal interaction, delay in the attainment of thermal equilibrium state, and uncertainty in specifying open boundaries and open boundary conditions of the regions, which are critically important in the analysis of the thermal conditions in receiving water bodies with tidal dominated, periodically reversing flow conditions. The results of an extensive study in the Hudson River at Indian Point, 42 miles upstream of the ocean end at the Battery, concluded that the tidal-transient, multi-dimensional discrete-element (UTA) thermal transport models (ESTONE, FLOTWO, TMPTWO computer codes) and the near-field far-field zone-matching methodology can be employed with a high degree of reliability in the assessment of the thermal impact of multi power plant operations on tidal dominated estuaries

  6. Operating experience of a portable thermophotovoltaic power supply

    Science.gov (United States)

    Becker, Frederick E.; Doyle, Edward F.; Shukla, Kailash

    1999-03-01

    Two configurations of man-portable thermophotovoltaic (TPV) power supplies based on Thermo Power's supported continuous fiber emitter have been designed, built, and are being tested. The systems use narrow-band, fibrous, ytterbia emitters radiating to bandgap matched silicon photovoltaic arrays with dielectric stack filters for optical energy recovery and recuperators for thermal energy recovery. The systems have been designed for operation with propane and with combustion air preheat temperatures of up to 1250 K. To operate at air preheat temperatures above the auto-ignition temperature of the fuel, a unique fuel delivery system was devised which results in the micromixing and rapid combustion of the fuel and air right in the emitter fibers. This allows the ytterbia emitter fibers to run much hotter (˜2000 K) than any of the surrounding structure.

  7. Management of nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    1984-01-01

    This Guide identifies the main objectives and responsibilities of management with respect to safe operation of nuclear power plants. The Guide discusses the factors to be considered in structuring the operating organization to meet these objectives, to establish the management programmes that assure the safety tasks are performed, and to see that the services and facilities needed to accomplish the tasks are available. The Guide is primarily addressed to safety matters directly related to the operating phase. It assumes, in other words, that the safety aspects of siting, design, manufacturing and construction have been resolved. However, it also covers the interrelationships between operations and design, construction and commissioning, including the involvement of the operating organization in appropriate reviews of safety issues with reference to the future operating phase. The Guide is mainly restricted to matters of principle in relation to management-level decision making aimed at establishing safety policies. It is therefore not suitable for implementing such policies at the operational level. The IAEA Codes of Practice and Safety Guides provide detailed guidance for the latter purpose in those areas considered appropriate

  8. Inpo programs for improvement of nuclear power plant operations

    International Nuclear Information System (INIS)

    Edward Moore, C.

    1989-01-01

    The talk shows how key INPO programs help foster improved nuclear power operations. The talk focuses on the results being seen from six key efforts: evaluations, training and accreditation, assistance, events analysis and information exchange, human performance and maintenance. The talk stresses that all INPO programs are geared toward enhanced performance and that progress in key performance areas since 1980 shows that INPO and U.S. industry efforts are achieving desired results

  9. Operational results from a physical power prediction model

    Energy Technology Data Exchange (ETDEWEB)

    Landberg, L [Risoe National Lab., Meteorology and Wind Energy Dept., Roskilde (Denmark)

    1999-03-01

    This paper will describe a prediction system which predicts the expected power output of a number of wind farms. The system is automatic and operates on-line. The paper will quantify the accuracy of the predictions and will also give examples of the performance for specific storm events. An actual implementation of the system will be described and the robustness demonstrated. (au) 11 refs.

  10. Three essential management processes of nuclear power plant operators

    International Nuclear Information System (INIS)

    Qi Tunfeng

    2010-01-01

    The paper takes the operation and management of Qinshan NPP Phase II as an example, focusing on the implementation of the essential process from the following three aspects the NPP production organization, training, examination and authorization for safety-related personnel, and financing budge management. A better understanding and implementation of the essential process will enable nuclear power plants to effectively control the nuclear safety from the most fundamental managerial level. (author)

  11. Contributions to economical and safe operation of nuclear power plants

    International Nuclear Information System (INIS)

    Ackermann, G.; Meyer, K.

    1989-01-01

    Selected results of scientific and technical research works in the Department 'Nuclear Power' of the Zittau Technical University are summarized which have been obtained on behalf of the Kombinat Kernkraftwerke 'Bruno Leuschner' and in conjunction with the education of scientific successors and have been partly adopted in textbooks. Works on improved utilization of nuclear fuel in pressurized water reactors are mentioned which, among other things, are related with the use of stretch-out mode of operation and optimization of nuclear fuel loading sequence. Results of experimental and theoretical investigations on coolant mixing in the reactor core are presented. A complex modelling of the dynamical long-term behaviour of nuclear power plants with pressurized water reactors due to xenon poisoning are briefly described. Finally, some results on noise diagnostics theory of power reactors are summarized. (author)

  12. Operating experience from Swedish nuclear power plants 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The total production of electricity from Swedish nuclear power plants was 69.2 TWh during 2001, which is an increase of more than 25% compared to 2000. The hydroelectric power production increased to 78.3 TWh, 22% more than during a normal year, i.e. a year with average rainfall. Wind power contributed 0.5 TWh, and remaining production sources, mainly from solid fuel plants combined with district heating, contributed 9.6 TWh. The electricity generation totalled 157.6 TWh, the highest annual production to date. The preliminary figures for export were 18.5 TWh and and for import 11.1 TWh. Operational statistics are presented for each Swedish reactor. Two events, given INES level 1 rating, are reported from Barsebaeck 2 and Ringhals 2.

  13. Operating experience from Swedish nuclear power plants 2001

    International Nuclear Information System (INIS)

    2002-01-01

    The total production of electricity from Swedish nuclear power plants was 69.2 TWh during 2001, which is an increase of more than 25% compared to 2000. The hydroelectric power production increased to 78.3 TWh, 22% more than during a normal year, i.e. a year with average rainfall. Wind power contributed 0.5 TWh, and remaining production sources, mainly from solid fuel plants combined with district heating, contributed 9.6 TWh. The electricity generation totalled 157.6 TWh, the highest annual production to date. The preliminary figures for export were 18.5 TWh and and for import 11.1 TWh. Operational statistics are presented for each Swedish reactor. Two events, given INES level 1 rating, are reported from Barsebaeck 2 and Ringhals 2

  14. Operating experience from Swedish nuclear power plants 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The total production of electricity from Swedish nuclear power plants was 65.6 TWh during 2002, which is a decrease compared to 2001. The energy capability factor for the 11 Swedish reactors averaged 80.8%. The PWRs at Ringhals averaged 87.6%, while the BWRs, not counting Oskarshamn 1, reached 89.2%. No events, which in accordance to conventions should be reported to IAEA, have occurred during 2002. Operational statistics are presented for each Swedish reactor. The hydroelectric power was 66 TWh, 16% lower than 2000. Wind power contributed 0.5 TWh, and remaining production sources, mainly from solid fuel plants combined with district heating, contributed 10.9 TWh. The electricity generation totalled 143 TWh, considerably less than the record high 2001 figure of 158.7 TWh. The preliminary figures for export were 14.8 TWh and and for import 20.1 TWh.

  15. Optimizing wellfield operation in a variable power price regime

    DEFF Research Database (Denmark)

    Bauer-Gottwein, Peter; Schneider, Raphael; Davidsen, Claus

    Wellfield management is a multi-objective optimization problem. One important management objective has been energy efficiency in terms of minimizing the energy footprint (EFP) of delivered water (MWh/m3). However, power systems in most countries are moving in the direction of deregulated power...... use itself. We estimated energy footprint as a function of wellfield pumping rate (EFP-Q relationship) for a wellfield in Denmark using a coupled well and pipe network model. This EFP-Q relationship was subsequently used in a stochastic dynamic programming framework to minimize total cost of operating...... the combined wellfield-storage-demand system over the course of a 2-year planning period based on a time series of observed price on the Danish power market and a deterministic, time-varying hourly water demand. In the SDP setup, hourly pumping rates are the decision variables. Constraints include storage...

  16. Knowledge base for power plant operation and its application to operation guide

    International Nuclear Information System (INIS)

    Doi, Atsushi; Sakaguchi, Toshiaki

    1986-01-01

    The present study is aimed at constructing a knowledge base for supervisory control operation in power plants and developing an operation guidance by using it. Examination is made to provide dignosis procedures on the basis of an existing alarm system. An operation guidance procedure for diagnosis is proposed which is to be followed when several alarms are sounded simultaneously in a power plant, and application of the procedure to an existing plant is examined. The operation manual for the plant includes 75 description items for six alarms. It is shown that the number of items related to these alarms can be reduced by 70 % by rearranging them according to the procedure. Another investigation is conducted to provide an operation manual for diagnosis to be used when one alarm is sounded in a plant. The quality of the manual developed is on nearly the same level with that for the existing plant examined. When a knowledge base is to be constructed from an existing operation manual, the processing operation generally requires a certain level of linguistic comprehension ability, such as for judgment of synonyms. It is demonstrated that the procedure proposed here is able to develop a high-quality knowledge base with standardized terminology. The procedure can also serve to construct operation manuals for plants in other industrial fields. (Nogami, K.)

  17. Optimal Operation of Interdependent Power Systems and Electrified Transportation Networks

    Directory of Open Access Journals (Sweden)

    M. Hadi Amini

    2018-01-01

    Full Text Available Electrified transportation and power systems are mutually coupled networks. In this paper, a novel framework is developed for interdependent power and transportation networks. Our approach constitutes solving an iterative least cost vehicle routing process, which utilizes the communication of electrified vehicles (EVs with competing charging stations, to exchange data such as electricity price, energy demand, and time of arrival. The EV routing problem is solved to minimize the total cost of travel using the Dijkstra algorithm with the input from EVs battery management system, electricity price from charging stations, powertrain component efficiencies and transportation network traffic conditions. Through the bidirectional communication of EVs with competing charging stations, EVs’ charging demand estimation is done much more accurately. Then the optimal power flow problem is solved for the power system, to find the locational marginal price at load buses where charging stations are connected. Finally, the electricity prices were communicated from the charging stations to the EVs, and the loop is closed. Locational electricity price acts as the shared parameter between the two optimization problems, i.e., optimal power flow and optimal routing problem. Electricity price depends on the power demand, which is affected by the charging of EVs. On the other hand, location of EV charging stations and their different pricing strategies might affect the routing decisions of the EVs. Our novel approach that combines the electrified transportation with power system operation, holds tremendous potential for solving electrified transportation issues and reducing energy costs. The effectiveness of the proposed approach is demonstrated using Shanghai transportation network and IEEE 9-bus test system. The results verify the cost-savings for both power system and transportation networks.

  18. The training of operating personnel at Spanish nuclear power plant

    International Nuclear Information System (INIS)

    Diaz, Antonio Burgos

    2011-01-01

    An essential condition in order to ensure that nuclear power plants are operated reliably and safely is the availability in the Control Room of duly qualified persons capable both of preventing accidents and of responding to them should they occur. Training of the Control Room operating crews is accomplished in two major stages: a lengthy process of initial training in which the knowledge acquired at high school and university is built upon, leading to the specialisation required to appropriately carry out the tasks to be performed in the Control Room, and a continuous training program aimed at maintaining and improving the knowledge and skills required to operate the plant, with feedback of the lessons learned from the industry's operating experience. The use of full-scope simulators replicating the physical conditions and environment of the Control Room allows the period of initial training to be reduced and is the most appropriate method for the continuous training program of the control room personnel, since these simulators increase the realism of the training scenarios, help to better understand the response of the plant and provide an accurate idea of transient response times. Tecnatom is the Training Centre for Spanish Operators; it is the 'Operator Training Factory' and its mission is to train the nuclear power plant operating personnel in both technological fundamentals and the development of diagnostic skills through practical scenarios on the simulator and on-the-job training. Our training programmes are based on a SAT (Systematic Approach to Training) methodology that has been implemented at both Spanish and overseas plants. (author)

  19. The control of operational risk in nuclear power plant operations - Some cross-cultural perspectives

    International Nuclear Information System (INIS)

    Suchard, A.; Rochlin, G.

    1992-01-01

    The operation of nuclear power plants requires the management of a complex technology under exacting performance and safety criteria. Organizations operating nuclear power plants are faced with the challenge of simultaneously meeting technical, organizational, and social demands, striving toward perfection in a situation where learning by trial and error can be too costly. In this process, they interact with regulatory bodies who seek to help minimize operational risk by imposing and upholding safety standards. The character of this interaction differs in various countries, as does the larger cultural setting. The study generally pursued the question of how organizations operating complex and demanding technologies adapt to such requirements and circumstances, and how they can succeed in delivering nearly error-free performance. One aspect of this study includes the comparison of organizational and cultural environments for nuclear power plant operations in the US, France, Germany, Sweden, and Switzerland. The research involved in-depth, continuous observations on location and interviews with plant personnel, especially control operators, at one plant in each country

  20. Wind Power Forecasting Error Frequency Analyses for Operational Power System Studies: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Florita, A.; Hodge, B. M.; Milligan, M.

    2012-08-01

    The examination of wind power forecasting errors is crucial for optimal unit commitment and economic dispatch of power systems with significant wind power penetrations. This scheduling process includes both renewable and nonrenewable generators, and the incorporation of wind power forecasts will become increasingly important as wind fleets constitute a larger portion of generation portfolios. This research considers the Western Wind and Solar Integration Study database of wind power forecasts and numerical actualizations. This database comprises more than 30,000 locations spread over the western United States, with a total wind power capacity of 960 GW. Error analyses for individual sites and for specific balancing areas are performed using the database, quantifying the fit to theoretical distributions through goodness-of-fit metrics. Insights into wind-power forecasting error distributions are established for various levels of temporal and spatial resolution, contrasts made among the frequency distribution alternatives, and recommendations put forth for harnessing the results. Empirical data are used to produce more realistic site-level forecasts than previously employed, such that higher resolution operational studies are possible. This research feeds into a larger work of renewable integration through the links wind power forecasting has with various operational issues, such as stochastic unit commitment and flexible reserve level determination.

  1. Economic Impact of Nuclear Power Plant in The Operational

    International Nuclear Information System (INIS)

    Sriyana

    2004-01-01

    Study on economic impact of nuclear power plant in the operational stage, in Madura has been conducted. The object of the study is SMART technology which is coupled with desalination installation. The power capacity is 2 x 100 M We and the water production capacity is 4 x 10,000 m 3 /day. This technology has been developed by Korea, but until recently there is no units in construction or operation. Input-Output analysis model is applied as the methodology of this study. Economic sector is aggregated from 56 x 56 to 10 x 10. This aggregation is meant to reduce the uncertainty in long term projection. This study conclude that : (1) In the operational stage SMART Nuclear Power Desalination will give an output to local economic about Rp 908.12 billion per year. (2) Electricity and water production will provide output direct impact to Madura about Rp. 1,234 trillion and will give direct impact to Regional Product Domestic Bruto (PDRB) about Rp. 138.7 billion. (3) Output impact to the electricity sector and fresh water sector is about 5.37% and 1.57% compared to PDRB 2018. (author)

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

    International Nuclear Information System (INIS)

    Powell, J.R.

    1977-01-01

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

  3. Validity and design of environmental surveillance systems for operating nuclear power plants. Final report

    International Nuclear Information System (INIS)

    Eichholz, G.G.

    1977-12-01

    The composition and procedures of environmental surveillance programs at completed and operating nuclear power plants have been examined with respect to their validity, continuing significance and cost. It was found that many programs contain components that are mainly an extension of preoperational baseline measurements that need not be continued indefinitely and that others lack the statistical validity to make their continued application meaningful. To identify the practical limits imposed by counting statistics and realistic equipment capacity measurements were done on iodine-131 and cesium-137 containing samples to establish detectability limits and proportionate costs for sample preparation and counting. It was found that under commercial conditions effective detectability limits and expected confidence limits were substantially higher than those mentioned in NRC Regulatory Guides. This imposes a need for either selecting fewer samples and counting them for longer times or accepting a lesser accuracy on more samples, within the bounds of reasonable cost per sample

  4. Environmental impact assessment of coal power plants in operation

    Directory of Open Access Journals (Sweden)

    Bartan Ayfer

    2017-01-01

    Full Text Available Coal power plants constitute an important component of the energy mix in many countries. However, coal power plants can cause several environmental risks such as: climate change and biodiversity loss. In this study, a tool has been proposed to calculate the environmental impact of a coal-fired thermal power plant in operation by using multi-criteria scoring and fuzzy logic method. We take into account the following environmental parameters in our tool: CO, SO2, NOx, particulate matter, fly ash, bottom ash, the cooling water intake impact on aquatic biota, and the thermal pollution. In the proposed tool, the boundaries of the fuzzy logic membership functions were established taking into account the threshold values of the environmental parameters which were defined in the environmental legislation. Scoring of these environmental parameters were done with the statistical analysis of the environmental monitoring data of the power plant and by using the documented evidences that were obtained during the site visits. The proposed method estimates each environmental impact factor level separately and then aggregates them by calculating the Environmental Impact Score (EIS. The proposed method uses environmental monitoring data and documented evidence instead of using simulation models. The proposed method has been applied to the 4 coal-fired power plants that have been operation in Turkey. The Environmental Impact Score was obtained for each power plant and their environmental performances were compared. It is expected that those environmental impact assessments will contribute to the decision-making process for environmental investments to those plants. The main advantage of the proposed method is its flexibility and ease of use.

  5. Environmental impact assessment of coal power plants in operation

    Science.gov (United States)

    Bartan, Ayfer; Kucukali, Serhat; Ar, Irfan

    2017-11-01

    Coal power plants constitute an important component of the energy mix in many countries. However, coal power plants can cause several environmental risks such as: climate change and biodiversity loss. In this study, a tool has been proposed to calculate the environmental impact of a coal-fired thermal power plant in operation by using multi-criteria scoring and fuzzy logic method. We take into account the following environmental parameters in our tool: CO, SO2, NOx, particulate matter, fly ash, bottom ash, the cooling water intake impact on aquatic biota, and the thermal pollution. In the proposed tool, the boundaries of the fuzzy logic membership functions were established taking into account the threshold values of the environmental parameters which were defined in the environmental legislation. Scoring of these environmental parameters were done with the statistical analysis of the environmental monitoring data of the power plant and by using the documented evidences that were obtained during the site visits. The proposed method estimates each environmental impact factor level separately and then aggregates them by calculating the Environmental Impact Score (EIS). The proposed method uses environmental monitoring data and documented evidence instead of using simulation models. The proposed method has been applied to the 4 coal-fired power plants that have been operation in Turkey. The Environmental Impact Score was obtained for each power plant and their environmental performances were compared. It is expected that those environmental impact assessments will contribute to the decision-making process for environmental investments to those plants. The main advantage of the proposed method is its flexibility and ease of use.

  6. Method for Prediction of the Power Output from Photovoltaic Power Plant under Actual Operating Conditions

    Science.gov (United States)

    Obukhov, S. G.; Plotnikov, I. A.; Surzhikova, O. A.; Savkin, K. D.

    2017-04-01

    Solar photovoltaic technology is one of the most rapidly growing renewable sources of electricity that has practical application in various fields of human activity due to its high availability, huge potential and environmental compatibility. The original simulation model of the photovoltaic power plant has been developed to simulate and investigate the plant operating modes under actual operating conditions. The proposed model considers the impact of the external climatic factors on the solar panel energy characteristics that improves accuracy in the power output prediction. The data obtained through the photovoltaic power plant operation simulation enable a well-reasoned choice of the required capacity for storage devices and determination of the rational algorithms to control the energy complex.

  7. Demand side resource operation on the Irish power system with high wind power penetration

    DEFF Research Database (Denmark)

    Keane, A.; Tuohy, A.; Meibom, Peter

    2011-01-01

    part of the power system plant mix and contribute to the flexible operation of a power system. A model for demand side resources is proposed here that captures its key characteristics for commitment and dispatch calculations. The model is tested on the all island Irish power system, and the operation...... of the functions of conventional peaking plant. Demand side resources are also shown to be capable of improving the reliability of the system, with reserve capability identified as a key requirement in this respect....... of the model is simulated over one year in both a stochastic and deterministic mode, to illustrate the impact of wind and load uncertainty. The results illustrate that demand side resources can contribute to the efficient, flexible operation of systems with high penetrations of wind by replacing some...

  8. Inhalation Exposure to PM-Bound Polycyclic Aromatic Hydrocarbons Released from Barbecue Grills Powered by Gas, Lump Charcoal, and Charcoal Briquettes.

    Science.gov (United States)

    Badyda, Artur J; Widziewicz, Kamila; Rogula-Kozłowska, Wioletta; Majewski, Grzegorz; Jureczko, Izabela

    2018-01-01

    The present study seeks to define the possible cancer risk arising from the inhalation exposure to particle (PM)-bound polycyclic aromatic hydrocarbons (PAHs) present in barbecue emission gases and to compare the risk depending on the type of fuel used for grill powering. Three types of fuel were compared: liquid propane gas, lump charcoal, and charcoal briquettes. PM 2.5 and PM 2.5-100 were collected during grilling. Subsequently, 16 PAHs congeners were extracted from the PM samples and measured quantitatively using gas chromatography. The content of PM-bound PAHs was used to calculate PAHs deposition in the respiratory tract using the multiple path particle dosimetry model. Finally, a probabilistic risk model was developed to assess the incremental lifetime cancer risk (ILCR) faced by people exposed to PAHs. We found a distinctly greater PAHs formation in case of grills powered by charcoal briquettes. The summary concentration of PAHs (Σ16PAH) ranged from inhale barbecue particles for 5 h a day, 40 days a year exceeds the acceptable level set by the U.S. Environmental Protection Agency. We conclude that the type of heat source used for grilling influences the PM-bound PAHs formation. The greatest concentration of PAHs is generated when grilling over charcoal briquettes. Loading grills with food generates conspicuously more PAHs emissions. Traditional grilling poses cancer risk much above the acceptable limit, as opposed to much less risk involving gas powered grills.

  9. Operational safety performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    2000-05-01

    Since the late 1980s, the IAEA has been actively sponsoring work in the area of indicators to monitor nuclear power plant (NPP) operational safety performance. The early activities were mainly focused on exchanging ideas and good practices in the development and use of these indicators at nuclear power plants. Since 1995 efforts have been directed towards the elaboration of a framework for the establishment of an operational safety performance indicator programme. The result of this work, compiled in this publication, is intended to assist NPPs in developing and implementing a monitoring programme, without overlooking the critical aspects related to operational safety performance. The framework proposed in this report was presented at two IAEA workshops on operational safety performance indicators held in Ljubljana, Slovenia, in September 1998 and at the Daya Bay NPP, Szenzhen, China, in December 1998. During these two workshops, the participants discussed and brainstormed on the indicator framework presented. These working sessions provided very useful insights and ideas which where used for the enhancement of the framework proposed. The IAEA is acknowledging the support and contribution of all the participants in these two activities. The programme development was enhanced by pilot plant studies. Four plants from different countries with different designs participated in this study with the objective of testing the applicability, usefulness and viability of this approach

  10. European clearinghouse on nuclear power plants operational experience feedback

    International Nuclear Information System (INIS)

    Ranguelova, Vesselina; Bruynooghe, Christiane; Noel, Marc

    2010-01-01

    Learning from operational experience and applying this knowledge promptly and intelligently is one of the ways to improve the safety of Nuclear Power Plant (NPP). Recent reviews of the effectiveness of Operational Experience Feedback (OEF) systems have pointed to the need for further improvement, with importance being placed on tailoring the information to the needs of the regulators. In 2007, at the request of a number of nuclear safety regulatory authorities in Europe, the Institute for Energy of the European Commission's Joint Research Centre (EC JRC) initiated a project on Nuclear Power Plant operational experience feedback, which adopts an integrated approach to the research needed to strengthen the European capabilities for assessment of NPP operational events and to promote the development of tools and mechanisms for the improved application of the lessons learned. Consequently, a so-called ''European Clearinghouse'' on NPP OEF was established, which includes scientific officers from the EC JRC, a number of European nuclear safety regulatory authorities and some of their Technical Support Organizations (TSOs). The paper discusses the activities implemented in 2008 within the framework of the European Clearinghouse on NPP OEF (hereinafter called the European NPP Clearinghouse) and provides an overview of the main conclusions drawn from the safety studies performed. Outlook of the activities carried out in 2009 are given. (orig.)

  11. Cyclic operation of power plant; Cyklisk drift av kraftvaermeverk

    Energy Technology Data Exchange (ETDEWEB)

    Storesund, Jan

    2007-12-15

    The great majority of power plants are designed for base load operation with a relatively small number of starts and stops per year. Therefore, there has been no need to consider fatigue at design. Over the last few years operation with more frequent starts and stops exists as a consequence of swinging electricity prices that has become common. This involves significantly higher frequency of damages; not least fatigue relates damages, and the number of severe failures in components that never before have had damage problems may increase as well. In the present work the different types of component that may suffer from cyclic operation related damage are gathered by a literature survey and described as follows: - where and how the damages comes up, - constructions that should be avoided, - non-destructive testing (NDT) for damage that may come up under cyclic operation, - calculation and assessment of integrity of critical components - areas where continued research would be valuable. Recommendations have been put together to be used to prevent cyclic operation related damage and to detect it in time. The target group for this study is i) plant owners of plants where cyclic operation is or may be present, ii) researchers in the area, and, iii) inspectors and NDT-operators. There are quite a number of components where cyclic operation has been found to significantly influence the lift time. Some of these components are described in many papers whereas occasional papers have been found for others. The amount of information that is possible to get for a certain component is likely related to its significance for cyclic operation damage. The most frequently reported problem is ligament cracking of high temperature headers. Other components where extensive studies have been done are: wall panels, creep-fatigue loaded welds and turbine components

  12. Operating the Irish power system with increased levels of wind power

    DEFF Research Database (Denmark)

    Tuohy, A.; Denny, E.; Meibom, Peter

    2008-01-01

    This paper summarises some of the main impacts of large amounts of wind power installed in the island of Ireland. Using results from various studies performed on this system, it is shown that wind power will impact on all time frames, from seconds to daily planning of the system operation. Results...... from studies examining operation of the system with up to approximately 40% of electricity provided by wind show that some of the most important aspects to be considered include the type of wind turbine technology, the provision of reserve to accommodate wind forecasting error and the method used...

  13. Energy Storage in Power System Operation: The Power Nodes Modeling Framework

    DEFF Research Database (Denmark)

    Heussen, Kai; Koch, Stephan; Ulbig, Andreas

    2010-01-01

    for designing operation strategies for power systems based on ubiquitous energy storage, for example to buer non-dispatchable generation, as well as for the evaluation of the operational performance in terms of energy eciency, reliability and cost. After introducing the modeling approach and a categorization......In this paper, a novel concept for the description of energy storage in power systems with dispatchable and non-dispatchable generators and loads is presented. It is based on a system-perspective consideration of energy storage, generation and consumption. This means that grid-relevant aspects...

  14. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans

    International Nuclear Information System (INIS)

    Feinroth, H.; Oldham, G.M.; Stiefel, J.T.

    1963-01-01

    This paper describes and evaluates five years of operation and test of the Shippingport Atomic Power Station and discusses the current technical developments and future plans of the Shippingport programme. This programme is directed towards development of the basic technology of light-water reactors to provide the basis for potential reduction in the costs of nuclear power. The Shippingport reactor plant has operated for over five years and has been found to integrate readily into a utility system either as a base load or peak load unit. Plant component performance has been reliable. There have been no problems in contamination or waste disposal. Access to primary coolant components for maintenance has been good, demonstrating the integrity of fuel elements. Each of the three refuelling operations performed since start-up of Shippingport has required successively less time to accomplish. Recently, the third seed was refuelled in 32 working days, about one quarter the time required for the first refuelling. The formal requirements of personnel training, written administrative procedures, power plant manuals, etc., which have been a vital factor in the successful implementation of the Shippingport programme, are described. The results obtained from the comprehensive test programme carried out at Shippingport are compared with calculations, and good agreement has been obtained. Reactor core performance, plant stability, and response to load changes, fuel element and control rod performance, long-term effects such as corrosion and radiation level build-up, component performance, etc., are discussed in this paper. The principal objective of the current and future programmes of the Shippingport Project in advancing the basic technology of water-cooled reactors is discussed. This programme includes the continued operation of the Shippingport plant, and the development, design, manufacture and test operation of a long-life, highpower density second core - Core 2. At its

  15. Thermal power plant operating regimes in future British power systems with increasing variable renewable penetration

    International Nuclear Information System (INIS)

    Edmunds, Ray; Davies, Lloyd; Deane, Paul; Pourkashanian, Mohamed

    2015-01-01

    Highlights: • This work investigates thermal power operating regimes in future power systems. • Gas plants have low utilisation in the scenarios considered. • Ramping intensity increases for gas plants and pumped storage. • Coal plants frequently operate at minimum stable levels and start-ups increase. • Grid emission intensity and total emission production remains substantial. - Abstract: This work investigates the operational requirements of thermal power plants in a number of potential future British power systems with increasing variable renewable penetration. The PLEXOS Integrated Energy Model has been used to develop the market models, with PLEXOS employing mixed integer programming to solve the unit commitment and economic dispatch problem, subject to a number of constraints. Initially, a model of the British power system was developed and validated. Subsequently, a 2020 test model was developed to analyse a number of future system structures with differing fuel and carbon prices and generation mixes. The study has found that in three of the four scenarios considered, the utilisation of gas power plants will be relatively low, but remains fundamental to the security of supply. Also, gas plants will be subject to more intense ramping. The findings have consequent implications for energy policy as expensive government interventions may be required to prevent early decommissioning of gas capacity, should the prevailing market conditions not guarantee revenue adequacy.

  16. French experience in operating pressurized water reactor power stations. Ten years' operation of the Ardennes power station

    International Nuclear Information System (INIS)

    Teste du Bailler, A.; Vedrinne, J.F.

    1978-01-01

    In the paper the experience gained over ten years' operation of the Ardennes (Chooz) nuclear power station is summarized from the point of view of monitoring and control equipment. The reactor was the first pressurized water reactor to be installed in France; it is operated jointly by France and Belgium. The equipment, which in many cases consists of prototypes, was developed for industrial use and with the experience that has now been gained it is possible to evaluate its qualities and defects, the constraints which it imposes and the action that has to be taken in the future. (author)

  17. IAEA Leads Operational Safety Mission to Muehleberg Nuclear Power Plant

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency today concluded a review of the safety practices at the Muehleberg Nuclear Power Plant (NPP) near Bern in Switzerland. The team noted a series of good practices and made recommendations and suggestions to reinforce them. The IAEA assembled the Operational Safety Review Team at the request of the Swiss government. The team, led by the IAEA's Division of Nuclear Installation Safety, performed an in-depth operational safety review from 8 to 25 October 2012. The team comprised experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Slovakia, Sweden, the United Kingdom and the United States as well as experts from the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Muehleberg NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry, Emergency Planning and Preparedness, Severe Accident Management and Long-Term Operation. The OSART team made 10 recommendations and 11 suggestions related to areas where operations of Muehleberg NPP could be further improved, for example: - Plant management could improve the operating experience program and methods throughout the plant to ensure corrective actions are taken in a timely manner; - In the area of Long-Term Operation, the ageing management review for some systems and components is not complete and the environmental qualification of originally installed safety cables has not yet been revalidated for long-term operation; and - The plant provisions for the protection of persons on the site during an emergency with radioactive release can be improved to minimize health risks to plant personnel. The team also identified 10 good

  18. Rocketdyne Propulsion & Power DOE Operations Annual Site Environmental Report 1996

    Energy Technology Data Exchange (ETDEWEB)

    Tuttle, R. J. [The Boeing Company, Canoga Park, CA (United States)

    1997-11-10

    This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by Rocketdyne Propulsion & Power of Boeing North American. Inc. (formerly Rockwell International Corporation). These are identified as the Santa Susana Field Laboratory (SSFL and the De Soto site. The sites have been used for manufacturing; R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The De Soto site essentially comprises office space and light industry with no remaining radiological operations, and has little potential impact on the environment. The SSFL site, because of its large size (2.668 acres), warrants comprehensive monitoring to ensure protection of the environment.

  19. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    Zagorski, J. F.

    1980-01-01

    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  20. Operating experience from Swedish nuclear power plants, 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The total generation of electricity from Swedish nuclear power plants was 70.1 TWh during 1999, which is slightly more than the mean value for the last five years. The total electricity consumption decreased by one percent, compared with 1998, to a total of 142.3 TWh, due to an unusually warm summer and autumn. The abundant supply of hydroelectric power resulted in comparatively extensive load-following operation by the nuclear plants during the year. Production losses due to low demand totalled 3.0 TWh. The closure of Barsebaeck 1 will result in a capacity reduction exceeding 4 TWh per year. The hydroelectric power production was 70 TWh, which was 6 TWh more than during a normal year, i.e. a year with average rainfall. The remaining production sources, mainly from solid fuel plants combined with district heating contributed 9 TWh. Electricity generation by means of wind power is still increasing. There are now about 470 wind power stations, which produced 0.3 TWh during the year. The total electricity generation totalled 149.8 TWh, a three percent decrease compared with 1998. The preliminary figures for export were 15.9 TWh and for import 8.4 TWh. The figures above are calculated from the preliminary production result. A comprehensive report on electric power supply and consumption in Sweden is provided in the 1999 Annual Report from the Swedish Power Association. The unit capability factor for the PWRs at Ringhals averaged 91%, while the BWRs averaged 82% mainly due to the extended outages. The BWR reactors at Forsmark averaged as much as 93%. Forsmark 1 experienced the shortest refuelling outage ever in Sweden, only 9 days and 20 hours. In May, Oskarshamn 2 passed a historical milestone - the unit produced 100 TWh since connection to the grid in 1974. The final production day for Barsebaeck 1, which had been in commercial operation since 1975, was on November 30 when a decision by the Swedish Government revoked the operating licence. Three safety-related events

  1. Existence of k⁻¹ power-law scaling in the equilibrium regions of wall-bounded turbulence explained by Heisenberg's eddy viscosity.

    Science.gov (United States)

    Katul, Gabriel G; Porporato, Amilcare; Nikora, Vladimir

    2012-12-01

    The existence of a "-1" power-law scaling at low wavenumbers in the longitudinal velocity spectrum of wall-bounded turbulence was explained by multiple mechanisms; however, experimental support has not been uniform across laboratory studies. This letter shows that Heisenberg's eddy viscosity approach can provide a theoretical framework that bridges these multiple mechanisms and explains the elusiveness of the "-1" power law in some experiments. Novel theoretical outcomes are conjectured about the role of intermittency and very-large scale motions in modifying the k⁻¹ scaling.

  2. Effect of wood fuels on power plant operability

    International Nuclear Information System (INIS)

    Orjala, M.; Ingalsuo, R.

    2001-01-01

    The objective of the research is to determine the critical properties of wood fuels on the basis of power plant operability, to determine the optimal conditions for reduction of harmful detriments, and to study how the storage and processing of wood fuels effect on the operability. Both the CFB and BFB technologies are studied. The project started in December 2000 and it will be ended by the end of 2002. Experts of the Fuels and Combustion research field of VTT Energy carry out the main parts of the research. Experts of the research field of Mineral Processing of VTT Chemical Technology, located in Outokumpu, and Kemian tutkimuspalvelut Oy/Oulu University, located in Outokumpu, participate in the analytics, and the research field of Materials and Manufacturing Technology of VTT Manufacturing Technology in Otaniemi participates in the research on material effects. System Technology Laboratory of Oulu University carries out the power plant automation and boiler control technology research under supervision of Professor Urpo Kortela. Co-operation with the materials research unit of EU's JRC, located in Petten, which started in the research 'Combustion of Forest Chips', will be continues in this research. Co-operation will be made with Swedish Vaermeforsk in the field of information exchange on experiences in utilisation of wood fuels in Swedish power plants and possibilities to join in the projects of Vaermeforsk in this research field. Following companies participate in the project: Etelae-Savon Energia Oy, Foster Wheeler Energia Oy, Kvaerner Pulping Oy, Simpele pasteboard factory of M-Real Oyj and Vaermeforsk AB (Sweden). (orig.)

  3. Ensuring safe operation at the Loviisa nuclear power plant

    International Nuclear Information System (INIS)

    Regnell, B.

    1985-01-01

    Safe operation of a nuclear plant can be achieved only if the plant is designed according to stringent safety principles, if the construction and commissioning work meets high standards and finally if proper attention is paid to the safety aspects in all operational activities. Clearly formulated safety principles and standards are required for all these steps. In the early phases of the Loviisa project only a few IAEA codes of practice and safety guides were available. Their usefulness was, however, felt early, and valuable guidance was offered by them in formulating the quality assurance programme, for example. The paper describes the approach taken in order to achieve high operational safety at the first nuclear power station in Finland, the Loviisa plant. The involvement in the project of the plant owner, Imatran Voima Oy (IVO), was very large, the company serving as its own architect-engineer. Experience has shown that the thorough knowledge of the plant, down to the finest details, obtained by extensive participation in design, erection and commissioning of the plant, is invaluable in the actual operation of the plant. This manifests itself most clearly in the event of malfunctions and incidents or if modifications have to be undertaken. Many different activities affecting the operational safety can be identified: actual operation of the plant, including the creation and maintaining of technical specifications, procedures, instructions, documentation systems, etc.; maintenance, repair and modification work; in-service inspection and testing practices; component failure data collection and analysis; incident reporting, collection and evaluation systems; operator training; quality assurance programme; procedures and implementation; reviews of operational safety by an independent safety committee; and supervision by the safety authorities. In the paper, all these activities are described in some detail. (author)

  4. Management quality in spanish nuclear power plant operation

    International Nuclear Information System (INIS)

    Perez de Zabalza Ramos, F.

    1995-01-01

    This paper analyzes the reasons that lead nuclear power plants to require engineering support that is not usual in other types of industrial installations, namely the complexity of the plant and the economic consequences of a possible shutdown. At the time of unit startup, the need to use the services of experienced engineers for the technical support of nuclear power plants induced plant owners to turn to the engineering companies which had participated in the design of the plants. The paper lists the wide range of plant support services which these engineering companies can provide, both from their central offices and on site, especially in the field of change orders and documentation update. The paper also describes the satisfactory development of management parameters in Spanish nuclear power plants both in terms of load factor and comparison of operating and maintenance costs, and how engineering companies have contributed to this achievement, by reducing costs with no loss in the technical quality of their services. Finally, the paper describes how the engineering companies have had to adapt to a shrinking market without losing quality and how they achieved this by diversifying their services. In this context there are two areas of concern. the first area of concern is the competition from certain companies with oversized staff, who attempt to employ them in operation support for nuclear power stations, a field which does not correspond to the training and background of said staff. This could lead to a loss of quality or economic efficiency of nuclear power plants, whose operation up to now has proven satisfactory. The second area of concern is the operator's tendency to use their own resources for engineering support, making more difficult the renewal of human resources and thus leading to a decrease in productivity, and in the transfer of practical and theoretical experience from one plant to another, as well as in the transmission of the latest know

  5. Operating experience and performance at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Mittal, Subhash; Gupta, J.P.

    1998-01-01

    Narora Atomic Power Station consists of two units of 220 MWe capacity each. These are Pressurized Heavy Water Reactors, fuelled by natural uranium, moderated and cooled by heavy water. The Station is owned by Nuclear Power Corporation of India Ltd., which is responsible for design, construction, commissioning, and operation of all nuclear power stations in the country. NAPS was the first opportunity to apply operating experiences in design, keeping in view the evolving safety and seismicity requirements, ease of maintenance, inservice inspection needs, improved construction ability and standardization. Both the units of NAPS are having improved safety standards of current international levels. All the equipment are indigenous with improved quality and reliability. The first unit of the station went critical in March 1989 and synchronized to the grid in July 1989. The second units followed with its criticality in October 1991 and synchronization in January 1992. Considering the initial stabilizing period, the performance of both units of NAPS has progressively improved over the years. The annual capacity factor for NAPS - 1 was 90.01% and for NAPS - 2 was 89.01% for the financial year 1997-1998. This paper presents an analysis of the performance during the last three years and measures taken to improve it. The stated enhanced performance could be achieved by improvement in human performance by training/re-training, scrupulous monitoring and review of equipment/systems, institution of adequate procedure and ensuring their adherence. (authors)

  6. Nevada Renewable Energy Training Project: Geothermal Power Plant Operators

    Energy Technology Data Exchange (ETDEWEB)

    Jim, Nichols [Truckee Meadows Community College, Reno, NV (United States)

    2014-04-29

    The purpose of this project was to develop and institute a training program for certified geothermal power plant operators (GPO). An advisory board consisting of subject matter experts from the geothermal energy industry and academia identified the critical skill sets required for this profession. A 34-credit Certificate of Achievement (COA), Geothermal Power Plant Operator, was developed using eight existing courses and developing five new courses. Approval from the Nevada System of Higher Education Board of Regents was obtained. A 2,400 sq. ft. geothermal/fluid mechanics laboratory and a 3,000 sq. ft. outdoor demonstration laboratory were constructed for hands-on training. Students also participated in field trips to geothermal power plants in the region. The majority of students were able to complete the program in 2-3 semesters, depending on their level of math proficiency. Additionally the COA allowed students to continue to an Associate of Applied Science (AAS), Energy Technologies with an emphasis in Geothermal Energy (26 additional credits), if they desired. The COA and AAS are stackable degrees, which provide students with an ongoing career pathway. Articulation agreements with other NSHE institutions provide students with additional opportunities to pursue a Bachelor of Applied Science in Management or Instrumentation. Job placement for COA graduates has been excellent.

  7. Shiraz solar power plant operation with steam engine

    International Nuclear Information System (INIS)

    Yaghoubi, M.; Azizian, K.

    2004-01-01

    The present industrial developments and daily growing need of energy, as well as economical and environmental problem caused by fossil fuels consumption, resulted certain constraint for the future demand of energy. During the past two decades great attention has been made to use renewable energy for different sectors. In this regard for the first time in Iran, design and construction of a 250 K W Solar power plant in Shiraz, Iran is being carried out and it will go to operation within next year. The important elements of this power plant is an oil cycle and a steam cycle, and several studies have been done about design and operation of this power plant, both for steady state and transient conditions. For the steam cycle, initially a steam turbine was chosen and due to certain limitation it has been replaced by a steam engine. The steam engine is able to produce electricity with hot or saturated vapor at different pressures and temperatures. In this article, the effects of installing a steam engine and changing its vapor inlet pressure and also the effects of sending hot or saturated vapor to generate electricity are studied. Various cycle performance and daily electricity production are determined. The effects of oil cycle temperature on the collector field efficiency, and daily, monthly and annual amount of electricity production is calculated. Results are compared with the steam cycle output when it contains a steam turbine. It is found that with a steam engine it is possible to produce more annual electricity for certain conditions

  8. CRISP. Dependable ICT Support of Power Grid Operations

    International Nuclear Information System (INIS)

    Gustavsson, R.; Mellstrand, P.; Tornqvist, B.; Akkermans, H.

    2005-03-01

    This deliverable D2.4 Dependable ICT support 0f Power Grid Operations is a link between deliverable D1.6 Information security models and their economics and planned activities in WP III, that is, Implementation, Experiments and Tests. Background CRISP material includes deliverables of D2.2 Design document and multi-agent simulation tool for distributed demand-supply matching and D2.3 Design document and simulation tool for diagnostics of high-DG power networks. Furthermore there are links between this document and the deliverable D1.7 Report on distributed network architectures and D1.8 Reports on case study simulations and results. In short, this document specifies and extends the general background on security models and dependability models of deliverable D1.6 with CRISP specific material of D2.2 and D2.4 towards the experiments and tests of WP III. The focus of this deliverable is on dependable ICT support of power grid operation. By recasting the three CRISP experiments into three Scenarios in Chapter 2 we claim that we have a good description of benefits and challenges related to future virtual utilities. Among the challenges are securing trustworthy operation from a technical operation side (avoid disturbances such as blackouts) as wee as from a user-centric business point of view (value added power related services). Our investigation on proper means to safeguard operations of future virtual utilities begins with an assessment of lessons learned from recent (2003) big blackouts worldwide in Chapter 3. We propose an accident diagnosis and repair model (STAMP in Section 3.2) suitable for the complex socio-technical system we envisage for future cell-based virtual utilities. From this analysis and the background material from deliverable D1.6 Information security models and their economics, we then reassess the dependability concerns related to the CRISP related scenarios of Chapter 2. The deliverable provides some novel ideas and models that we claim are

  9. CRISP. Dependable ICT Support of Power Grid Operations

    Energy Technology Data Exchange (ETDEWEB)

    Gustavsson, R.; Mellstrand, P.; Tornqvist, B. [Blekinge Institute of Technology BTH, Karlskrona (Sweden); Akkermans, H. [EnerSearch, Malmoe (Sweden)

    2005-03-15

    This deliverable D2.4 Dependable ICT support 0f Power Grid Operations is a link between deliverable D1.6 Information security models and their economics and planned activities in WP III, that is, Implementation, Experiments and Tests. Background CRISP material includes deliverables of D2.2 Design document and multi-agent simulation tool for distributed demand-supply matching and D2.3 Design document and simulation tool for diagnostics of high-DG power networks. Furthermore there are links between this document and the deliverable D1.7 Report on distributed network architectures and D1.8 Reports on case study simulations and results. In short, this document specifies and extends the general background on security models and dependability models of deliverable D1.6 with CRISP specific material of D2.2 and D2.4 towards the experiments and tests of WP III. The focus of this deliverable is on dependable ICT support of power grid operation. By recasting the three CRISP experiments into three Scenarios in Chapter 2 we claim that we have a good description of benefits and challenges related to future virtual utilities. Among the challenges are securing trustworthy operation from a technical operation side (avoid disturbances such as blackouts) as wee as from a user-centric business point of view (value added power related services). Our investigation on proper means to safeguard operations of future virtual utilities begins with an assessment of lessons learned from recent (2003) big blackouts worldwide in Chapter 3. We propose an accident diagnosis and repair model (STAMP in Section 3.2) suitable for the complex socio-technical system we envisage for future cell-based virtual utilities. From this analysis and the background material from deliverable D1.6 Information security models and their economics, we then reassess the dependability concerns related to the CRISP related scenarios of Chapter 2. The deliverable provides some novel ideas and models that we claim are

  10. Preliminary study on psychosomatic status of nuclear power plant operators

    International Nuclear Information System (INIS)

    Bi Jinling; Liu Yulong; Li Yuan; Bian Huahui; Sun Yiling; Qiu Mengyue; Liu Chunfeng

    2011-01-01

    Objective: To understand the operators' psychosomatic health status in nuclear power plant; and provide the scientific basis of measures for preventing and reducing mental disorders in operators. Methods: The Psychosomatic Health Battery (PSHB) was used to assess the psychosomatic health status in 109 operators who were random selected from Qinshan nuclear power plant, etc. They were tested from lie, emotional stability, liveliness, tension, apprehension, mental health, such as psychopathic deviatesuch 7 personality traits. Results: Lie < 8, all inspected groups were normal. Psychopathic deviate: 98.2% for normal group 0.9% for both of groups occurred possible mental health problems and confirmed mental health problems; Mental health: 80.7% (88/109) for fine mental health ones, 29.4% (32/109) for those with excellent mental health, 51.4% (56/109) for good mental health ones, 13.8% (15/109) for general mental health ones, 5.5% (6/109) for poor mental health ones. Age factor could influence the mean values of the factors of apprehension, tension, mental health and psychopathic deviate. Correlation analysis showed that there was a correlation between tension and psychopathic deviate (r=0.664, P<0.01), and the other correlation coefficient was between apprehension and mental health (r=-0.789, P<0.01). Conclusions: There is an excellent condition of psychosomatic health in most of the operators, however, there are still a very small percentage of psychosomatic disorders among these operators, to improve the quality of their psychosomatic health, psychological counseling should be particularly strengthened to those with problems of psychosomatic health. (authors)

  11. Contribution of quality assurance to effective nuclear power plant operation

    International Nuclear Information System (INIS)

    Raisic, N.

    1984-01-01

    The regulatory requirements related to quality assurance (QA) serve as an effective mechanism in establishing and implementing the QA programme during the design, construction and operation of nuclear power plants. However, these requirements only relate to the equipment and activities concerning the safety of nuclear power plants; the decision as to their implementation on other non-safety-related equipment is left to the plant management. As a result, operation statistics show that the safety-related systems are performing satisfactorily and that they are not of serious concern to plant unavailability. On the other hand, non-safety-related equipment which is still vital to plant performances is more frequently responsible for plant outages and losses in electricity production. QA programmes implemented on such equipment are in principle less strict, unsystematic and, in a number of cases, non-existent. An attempt has been made to analyse the existing operating experience data in order to identify the correlation of outage statistics with QA programmes required by existing standards and their implementation practices, both in respect of programme coverage and intensity. Unfortunately, existing operating experience data cannot directly correlate plant performance with the QA programmes implemented in order to demonstrate the effectiveness of QA techniques to plant safety, reliability of plant equipment and plant availability. For these reasons an analysis is made of outage statistics to identify the modes and causes of outages and to relate them to existing QA requirements and practices. Some conclusions are deduced that relate to a possible improvement of plant performance by consequent implementation of QA requirements to the equipment and activities responsible for both plant safety and efficient electricity production, and by adequate grading of QA activities to obtain a cost-effective QA programme in plant operation. (author)

  12. Toward autonomous operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, M.

    1994-01-01

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

  13. Genetic algorithms applied to the nuclear power plant operation

    International Nuclear Information System (INIS)

    Schirru, R.; Martinez, A.S.; Pereira, C.M.N.A.

    2000-01-01

    Nuclear power plant operation often involves very important human decisions, such as actions to be taken after a nuclear accident/transient, or finding the best core reload pattern, a complex combinatorial optimization problem which requires expert knowledge. Due to the complexity involved in the decisions to be taken, computerized systems have been intensely explored in order to aid the operator. Following hardware advances, soft computing has been improved and, nowadays, intelligent technologies, such as genetic algorithms, neural networks and fuzzy systems, are being used to support operator decisions. In this chapter two main problems are explored: transient diagnosis and nuclear core refueling. Here, solutions to such kind of problems, based on genetic algorithms, are described. A genetic algorithm was designed to optimize the nuclear fuel reload of Angra-1 nuclear power plant. Results compared to those obtained by an expert reveal a gain in the burn-up cycle. Two other genetic algorithm approaches were used to optimize real time diagnosis systems. The first one learns partitions in the time series that represents the transients, generating a set of classification centroids. The other one involves the optimization of an adaptive vector quantization neural network. Results are shown and commented. (orig.)

  14. Hydropower operations data management at Bonneville Power Administration

    International Nuclear Information System (INIS)

    Dies, R.

    2006-01-01

    The decision support software used by Bonneville Power Administration (BPA) in its operation of the Federal Columbia River Power System in the Pacific northwest was presented along with examples of water resources data and information regarding weather and stream flow. Water resources data is used extensively in hydropower operations for planning purposes through to real-time operations. This includes long-term historical hydrology and realtime system information on snow cover, river discharges and water elevations. Since the data comes from many different sources, the quality and frequency varies, with sample intervals ranging from seconds to days. Some data may be intermittent and transmitted only when thresholds are reached. Data can be communication via SCADA telemetry, the Internet, direct satellite feed, telephone or fax. The key requirement for a decision support system is the reliable and easily accessed compilation of all this data. The BPA uses long-term planning models, system-wide generation scheduling applications, and near-real-time optimization of generating units. It was suggested that the hydrologic forecasting community could benefit from the utility's experience using these applications. tabs., figs

  15. Cognitive skill training for nuclear power plant operational decision making

    Energy Technology Data Exchange (ETDEWEB)

    Mumaw, R.J.; Swatzler, D.; Roth, E.M. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Thomas, W.A. [Quantum Technologies, Inc., Oak Brook, IL (United States)

    1994-06-01

    Training for operator and other technical positions in the commercial nuclear power industry traditionally has focused on mastery of the formal procedures used to control plant systems and processes. However, decisionmaking tasks required of nuclear power plant operators involve cognitive skills (e.g., situation assessment, planning). Cognitive skills are needed in situations where formal procedures may not exist or may not be as prescriptive, as is the case in severe accident management (SAM). The Westinghouse research team investigated the potential cognitive demands of SAM on the control room operators and Technical Support Center staff who would be most involved in the selection and execution of severe accident control actions. A model of decision making, organized around six general cognitive processes, was developed to identify the types of cognitive skills that may be needed for effective performance. Also, twelve SAM scenarios were developed to reveal specific decision-making difficulties. Following the identification of relevant cognitive skills, 19 approaches for training individual and team cognitive skills were identified. A review of these approaches resulted in the identification of general characteristics that are important in effective training of cognitive skills.

  16. Cognitive skill training for nuclear power plant operational decision making

    International Nuclear Information System (INIS)

    Mumaw, R.J.; Swatzler, D.; Roth, E.M.; Thomas, W.A.

    1994-06-01

    Training for operator and other technical positions in the commercial nuclear power industry traditionally has focused on mastery of the formal procedures used to control plant systems and processes. However, decisionmaking tasks required of nuclear power plant operators involve cognitive skills (e.g., situation assessment, planning). Cognitive skills are needed in situations where formal procedures may not exist or may not be as prescriptive, as is the case in severe accident management (SAM). The Westinghouse research team investigated the potential cognitive demands of SAM on the control room operators and Technical Support Center staff who would be most involved in the selection and execution of severe accident control actions. A model of decision making, organized around six general cognitive processes, was developed to identify the types of cognitive skills that may be needed for effective performance. Also, twelve SAM scenarios were developed to reveal specific decision-making difficulties. Following the identification of relevant cognitive skills, 19 approaches for training individual and team cognitive skills were identified. A review of these approaches resulted in the identification of general characteristics that are important in effective training of cognitive skills

  17. De-regulated electric power markets and operating nuclear power plants: the case of British energy

    International Nuclear Information System (INIS)

    Hewlett, James G.

    2005-01-01

    One issue addressed in almost all electric power restructuring/de-regulation plans in both the United States (US) and the United Kingdom (UK) was the recovery of operating nuclear power plant's spent fuel disposal costs and the expenditures to decommission the units when they are retired. Prior to restructuring, in theory at least, in both countries, electricity consumers were paying for the back end costs from operating nuclear power plants. Moreover, in virtually all cases in the US, states included special provisions to insure that consumers would continue to do so after power markets were de-regulated. When power markets in the UK were initially restructured/de-regulated and nuclear power privatized, the shareholders of British Energy (BE) were initially responsible for these costs. However, after electricity prices fell and BE collapsed, the British government shifted many of the costs to future taxpayers, as much as a century forward. If this was not done, the book value of BE's equity would have been about -3.5 billion pounds. That is, BE's liabilities would have been about -3.5 billion pounds greater than their assets. It is difficult to see how BE could remain viable under such circumstances

  18. HEMP emergency planning and operating procedures for electric power systems. Power Systems Technology Program

    Energy Technology Data Exchange (ETDEWEB)

    Reddoch, T.W.; Markel, L.C. [Electrotek Concepts, Inc., Knoxville, TN (United States)

    1991-12-31

    Investigations of the impact of high-altitude electromagnetic pulse (HEMP) on electric power systems and electrical equipment have revealed that HEMP creates both misoperation and failures. These events result from both the early time E{sub 1} (steep-front pulse) component and the late time E{sub 3} (geomagnetic perturbations) component of HEMP. In this report a HEMP event is viewed in terms of its marginal impact over classical power system disturbances by considering the unique properties and consequences of HEMP. This report focuses on system-wide electrical component failures and their potential consequences from HEMP. In particular, the effectiveness of planning and operating procedures for electric systems is evaluated while under the influence of HEMP. This assessment relies on published data and characterizes utilities using the North American Electric Reliability Council`s regions and guidelines to model electric power system planning and operations. Key issues addressed by the report include how electric power systems are affected by HEMP and what actions electric utilities can initiate to reduce the consequences of HEMP. The report also reviews the salient features of earlier HEMP studies and projects, examines technology trends in the electric power industry which are affected by HEMP, characterizes the vulnerability of power systems to HEMP, and explores the capability of electric systems to recover from a HEMP event.

  19. 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

  20. Spent fuel cask handling at an operating nuclear power plant

    International Nuclear Information System (INIS)

    Pal, A.C.

    1988-01-01

    The importance of spent fuel handling at operating nuclear power plants cannot be overstated. Because of its highly radioactive nature, however, spent fuel must be handled in thick, lead-lined containers or casks. Thus, all casks for spent fuel handling are heavy loads by the US Nuclear Regulatory Commission's definition, and any load-drop must be evaluated for its potential to damage safety-related equipment. Nuclear Regulatory Guide NUREG-0612 prescribes the regulatory requirements of alternative heavy-load-handling methodologies such as (a) by providing cranes that meet the requirements of NUREG-0554, which shall be called the soft path, or (b) by providing protective devices at all postulated load-drop areas to prevent any damage to safety-related equipment, which shall be called the hard path. The work reported in this paper relates to cask handling at New York Power Authority's James A. FitzPatrick (JAF) plant

  1. (Shippingport Atomic Power Station). Quarterly operating report, fourth quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    At the beginning of the fourth quarter of 1980, the Shippingport Atomic Power Station remained shutdown for the normally planned semiannual maintenance and testing program, initiated September 12, 1980. Operational testing began on November 7. Maximum power was achieved November 28 and was maintained throughout the remainder of the quarter except as noted. The LWBR Core has generated 19,046.07 EFPH from start-up through the end of the quarter. During this quarter, approximately 0.000025 curies of Xe 133 activity were released from the station. During the fourth quarter of 1980, 1081 cubic feet of radioactive solid waste was shipped out of state for burial. These shipments contained 0.037 curies of radioactivity.

  2. Short-Term Wind Speed Forecasting for Power System Operations

    KAUST Repository

    Zhu, Xinxin

    2012-04-01

    The emphasis on renewable energy and concerns about the environment have led to large-scale wind energy penetration worldwide. However, there are also significant challenges associated with the use of wind energy due to the intermittent and unstable nature of wind. High-quality short-term wind speed forecasting is critical to reliable and secure power system operations. This article begins with an overview of the current status of worldwide wind power developments and future trends. It then reviews some statistical short-term wind speed forecasting models, including traditional time series approaches and more advanced space-time statistical models. It also discusses the evaluation of forecast accuracy, in particular, the need for realistic loss functions. New challenges in wind speed forecasting regarding ramp events and offshore wind farms are also presented. © 2012 The Authors. International Statistical Review © 2012 International Statistical Institute.

  3. Optimizing Wellfield Operation in a Variable Power Price Regime

    DEFF Research Database (Denmark)

    Bauer-Gottwein, Peter; Schneider, Raphael; Davidsen, Claus

    2016-01-01

    Wellfield management is a multiobjective optimization problem. One important objective has been energy efficiency in terms of minimizing the energy footprint (EFP) of delivered water (MWh/m3). However, power systems in most countries are moving in the direction of deregulated markets and price...... itself. We estimated EFP of pumped water as a function of wellfield pumping rate (EFP-Q relationship) for a wellfield in Denmark using a coupled well and pipe network model. This EFP-Q relationship was subsequently used in a Stochastic Dynamic Programming (SDP) framework to minimize total cost...... of operating the combined wellfield-storage-demand system over the course of a 2-year planning period based on a time series of observed price on the Danish power market and a deterministic, time-varying hourly water demand. In the SDP setup, hourly pumping rates are the decision variables. Constraints include...

  4. Summary of Operating Experience in Swiss Nuclear Power Plants 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-15

    The five Swiss nuclear power units produced a net total of 23.6 TWh of electricity in 1999 - not as high as the all-time record (24.45 TWh in 1998), but nonetheless a solid operational performance. The nuclear share in overall electricity production was 35.3%, again lower than the previous year's 40%. In general, plant operation in 1999 was practically as undisturbed and as reliable as in 1998, reflecting the ongoing tradition of careful maintenance that contributes so much to keeping the plants in excellent condition. However, due to exceptional outage activities at Beznau 2 (steam generator replacement) and an unplanned shut-down at Goesgen to replace a hydrogen seal on the main generator, 1999 nuclear production could not match that of the previous year. Also, record hydro power production caused the nuclear share in total electricity production to drop. With the exception of Beznau 2, all refueling and maintenance outages were once again short. The Leibstadt outage lasted 26 days, Goesgen 33 days, Beznau 1 lasted 29 days, Beznau 2 89 days and Muehleberg 27 days. At Goesgen, MOX fuel was loaded for the third time in 1999. Of the 44 freshly-loaded fuel elements, 20 were MOX elements. Non-electrical energy supplies from the Beznau and Goesgen nuclear power plants functioned flawlessly. Beznau fed 143.6 GWh of heat energy into the Refuna district heating system, while Goesgen supplied 169 GWh of process heat to the neighboring Niedergoesgen cardboard factory. At the end of 1999 and the beginning of 2000 all Swiss nuclear units continued to operate flawlessly - notwithstanding the challenges posed by the 'Lothar' storm that hit Western Europe in late December and the so-called Y2K computer bug that threatened to hit shortly afterwards, during the 'millennial' change-over. (authors)

  5. Summary of Operating Experience in Swiss Nuclear Power Plants 1999

    International Nuclear Information System (INIS)

    2000-05-01

    The five Swiss nuclear power units produced a net total of 23.6 TWh of electricity in 1999 - not as high as the all-time record (24.45 TWh in 1998), but nonetheless a solid operational performance. The nuclear share in overall electricity production was 35.3%, again lower than the previous year's 40%. In general, plant operation in 1999 was practically as undisturbed and as reliable as in 1998, reflecting the ongoing tradition of careful maintenance that contributes so much to keeping the plants in excellent condition. However, due to exceptional outage activities at Beznau 2 (steam generator replacement) and an unplanned shut-down at Goesgen to replace a hydrogen seal on the main generator, 1999 nuclear production could not match that of the previous year. Also, record hydro power production caused the nuclear share in total electricity production to drop. With the exception of Beznau 2, all refueling and maintenance outages were once again short. The Leibstadt outage lasted 26 days, Goesgen 33 days, Beznau 1 lasted 29 days, Beznau 2 89 days and Muehleberg 27 days. At Goesgen, MOX fuel was loaded for the third time in 1999. Of the 44 freshly-loaded fuel elements, 20 were MOX elements. Non-electrical energy supplies from the Beznau and Goesgen nuclear power plants functioned flawlessly. Beznau fed 143.6 GWh of heat energy into the Refuna district heating system, while Goesgen supplied 169 GWh of process heat to the neighboring Niedergoesgen cardboard factory. At the end of 1999 and the beginning of 2000 all Swiss nuclear units continued to operate flawlessly - notwithstanding the challenges posed by the 'Lothar' storm that hit Western Europe in late December and the so-called Y2K computer bug that threatened to hit shortly afterwards, during the 'millennial' change-over. (authors)

  6. POWER LOSSES ASSESSMENT IN TRANSFORMERS AFTER THE NORMATIVE OPERATING PERIOD

    Directory of Open Access Journals (Sweden)

    M. I. Fursanov

    2015-01-01

    Full Text Available The capacity losses values both loading and off-load are topmost parameters characterizing the distribution mains customers’ transformers operating effectiveness. Precise determination of the specified values facilitates substantiated choice of the optimizing procedures. The actuality of the given topic increases owing to the fact that the modern electric grid utilizes plenty of the oil-transformers whose time in commission considerably exceeds the statutory 25 years. Under the conditions of continued operation the power-losses measurement according to the functioning guidelines does not seem always possible.The authors present an improved power-losses assessment technique based on the currently accepted thermal model of the oil-transformer. They indicate the deficiency of the existing technique and substantiate some of the changes in practical application of the mathematical model. The article makes an emphasis on peculiarities of the temperature changes in the oil-transformer and offers a prototype device of open architecture for realizing the improved technique of the power-losses measurement. The paper describes the device design features and functionality options and depicts its sketchy schematic. The authors note the potential of additional to assessing the power-losses volume, transmitting the obtained information to the dispatcher  via  GSM-connection  for  simplification  of  the  transformer  status  monitoring; as well as the capability of integrating the device into the system of the transformer thermal protection. The practical merit and application scope of the obtained results are in development and choice of the optimizing measures to be taken in the distributive electrical grids, e. g. the transformer replacement.

  7. Optimizing Wellfield Operation in a Variable Power Price Regime.

    Science.gov (United States)

    Bauer-Gottwein, Peter; Schneider, Raphael; Davidsen, Claus

    2016-01-01

    Wellfield management is a multiobjective optimization problem. One important objective has been energy efficiency in terms of minimizing the energy footprint (EFP) of delivered water (MWh/m(3) ). However, power systems in most countries are moving in the direction of deregulated markets and price variability is increasing in many markets because of increased penetration of intermittent renewable power sources. In this context the relevant management objective becomes minimizing the cost of electric energy used for pumping and distribution of groundwater from wells rather than minimizing energy use itself. We estimated EFP of pumped water as a function of wellfield pumping rate (EFP-Q relationship) for a wellfield in Denmark using a coupled well and pipe network model. This EFP-Q relationship was subsequently used in a Stochastic Dynamic Programming (SDP) framework to minimize total cost of operating the combined wellfield-storage-demand system over the course of a 2-year planning period based on a time series of observed price on the Danish power market and a deterministic, time-varying hourly water demand. In the SDP setup, hourly pumping rates are the decision variables. Constraints include storage capacity and hourly water demand fulfilment. The SDP was solved for a baseline situation and for five scenario runs representing different EFP-Q relationships and different maximum wellfield pumping rates. Savings were quantified as differences in total cost between the scenario and a constant-rate pumping benchmark. Minor savings up to 10% were found in the baseline scenario, while the scenario with constant EFP and unlimited pumping rate resulted in savings up to 40%. Key factors determining potential cost savings obtained by flexible wellfield operation under a variable power price regime are the shape of the EFP-Q relationship, the maximum feasible pumping rate and the capacity of available storage facilities. © 2015 The Authors. Groundwater published by Wiley

  8. Argentina's operator support systems in nuclear power plants

    International Nuclear Information System (INIS)

    Goldstein, M.; Palamidessi, H.

    1996-01-01

    The development of operator support systems for nuclear power plants started in Argentina a few years ago. Four systems are at present deployed or under development. The participation of utility personnel in the co-ordinated research program has helped in revising the current experience and in selecting and specifying the systems to be developed and the resources needed for their implementation. Main efforts will be aimed to the selection of those systems that can be more easily implemented, to improve the data retrieval and handling, to develop diverse supplies of software products and to promote the understanding of support systems among the potential end users. (author). 12 refs

  9. Human equation in operating a nuclear-power plant

    International Nuclear Information System (INIS)

    Barrett, R.S.

    1982-01-01

    The accident at Three Mile Island has forced the nuclear industry to acknowledge a badly neglected aspect of nuclear-power-plant safety - the human equation. The industry now appears to recognize the importance of operator selection, training, motivation, and licensing, and the need to design a system from the point of view of communication, information retrieval, record keeping, and human factors psychology. As a result, the relatively small initiatives that were begun a few years ago by the EPRI are now being greatly expanded

  10. Operating experience with diesel generators in Belgian nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Merny, R. [Association Vincotte, Avenue du Roi 157, B-1060 Bruxelles/Brussels (Belgium)

    1986-02-15

    Various problems have occurred on the diesel generators in the Belgian nuclear power plants, independently of the D.G. manufacturer or from the operating crew. Furthermore no individual part of the D.G. can be incriminated as being the main cause of the incidents. The incidents reported in this paper are chosen because of the importance for the safety or for the long repair period. The unavailability of a D.G. can only be detected by periodic tests and controls. Combined with a good preventive maintenance, the risks of incidents can be reduced. (author)

  11. Operating experience with diesel generators in Belgian nuclear power plants

    International Nuclear Information System (INIS)

    Merny, R.

    1986-01-01

    Various problems have occurred on the diesel generators in the Belgian nuclear power plants, independently of the D.G. manufacturer or from the operating crew. Furthermore no individual part of the D.G. can be incriminated as being the main cause of the incidents. The incidents reported in this paper are chosen because of the importance for the safety or for the long repair period. The unavailability of a D.G. can only be detected by periodic tests and controls. Combined with a good preventive maintenance, the risks of incidents can be reduced. (author)

  12. Design of a Power Tool Attachment for Sawing Operation

    Directory of Open Access Journals (Sweden)

    Mayur Appaiah

    2015-07-01

    Full Text Available The Design of a Power Tool Attachment for Sawing Operation is discussed. First, the Target Specifications are established. The Design work is carried out, especially that of the Main Shaft and Support Tube. Calculations and Finite Element Analysis (FEA are also done. The Prototype is fabricated and assembled. The Testing of the prototype is done, by Sawing commercial plywood of maximum thickness 25mm. Weight of the Attachment is 1.3 kg, and the Machine is easy to use, benefitting unskilled users.

  13. Nuclear power plant control room operators' performance research

    International Nuclear Information System (INIS)

    Gray, L.H.; Haas, P.M.

    1984-01-01

    A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis

  14. Human factors in the operation of nuclear power plants

    International Nuclear Information System (INIS)

    Swaton, E.; Neboyan, V.; Lederman, L.

    1987-01-01

    In large and complex interactive systems, human error can contribute substantially to system failures. At nuclear power plants, operational experience demonstrates that human error accounts for a considerable proportion of safety-related incidents. However, experience also shows that human intervention can be very effective if there is a thorough understanding of the situation in the plant. Thus, an efficient interface of man and machine is important not only to prevent human errors but also to assist the operator in coping with unforeseen events. Human reliability can be understood as a qualitative as well as a quantitative term. Qualitatively it can be described as the aim for successful human performance of activities necessary for system reliability and availability. Quantitatively, it refers to data on failure rates or error probabilities that can be used, for example, for probabilistic safety assessments

  15. Quality assurance during operation of nuclear power plants

    International Nuclear Information System (INIS)

    Modemann, G.

    1990-01-01

    The demands of the licensing authorities and the Nuclear Safety Regulations (KTA Rules) on the one hand and the utility's requirements on the other hand have led to the quality assurance system for the operation of nuclear power plants. One part of the system is the organizational structure for the distribution of all tasks and responsibilities to qualified staff members; all checks are carried out by experts who are independent of the executing staff if necessary. The other part of the system comprises the procedural structures for operation, maintenance, inspection, repair and modifications as well as for procurement and preparation of materials and spare parts. The application and efficiency of the quality assurance system is supervised and periodically checked by an independent department. (orig.) [de

  16. Psychosocial aspect of safe operation in Japanese nuclear power plants

    International Nuclear Information System (INIS)

    Kuroda, Isao

    1988-01-01

    It is not easy to reveal the reasons of safe operation of N.P.P. because many complicated factors are interrelated. However, to clarify the effective factors of the recent safe operation of Japanese N.P.P. is the important thema of research to continue this condition and the more improved level. At present, the follwing factors can be pointed out; 1) Influential safety policy of regulatory structures. 2) Enthusiastic and careful company policy on N.P.P. safety. 3) Close and stable relationship of the industries with companies on research, training and maintenance. 4) Collaborated safety research among scientific facilities, companies and manufacturers. 5) Good organization and management for N.P.P. personnel. 6) Well organized training program in company and training facilities. 7) Highly motivated N.P.P. personnel with high educational background. 8) Company atmosphere on N.P.P. safety. 9) Public opinion on nuclear power safety. (author)

  17. Expert systems in power substation operation and control

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Guilherme Moutinho; Lambert-Torres, Germano; Silva, Alexandre P. Alves da [Escola Federal de Engenharia de Itajuba, MG (Brazil)

    1994-12-31

    With digital technology being increasingly adopted in power substations (SE), perspectives are created for integration of supervision, control and protection systems in addition to making its process automation feasible. Once a SE is digitalized, the systems which previously were implemented physically will be able to be implemented by means of computer programs (software), allowing the expansion of its scope of operation. Studies and research performed at the international level have pointed to the utilization of Expert Systems (ES) as a more suitable alternative for representation and solution of the operation and control problems, especially those which do not have an established theory, which are provided with diagnosis characteristics and that associate themselves with fuzzy data and information. (author) 4 refs., 3 figs.

  18. Classification of nuclear power plant operator support systems

    International Nuclear Information System (INIS)

    Alpeev, A.S.

    1994-01-01

    The objective of this survey was to examine the general characteristics of modern nuclear power plant process monitoring/control systems and to apply developing technology (intellectual automation) in order to improve the man-machine interface. The support systems that implement each phase of the control function...information, assessment, decision-making, and implementation...were discussed, and where applicable, intellectual automation was applied to the support system. It was concluded that the application of intellectual automation, as well as other (undefined) possibilities for improving the man-machine interface, would relieve the operator of many routine activities and allow him to readily apply high potential to those poorly-formalized scenarios in which the operator's work can't be automated. It was also concluded that the development of such support systems would not be without problems, i.e. software certification, traning, and jurisdictional questions

  19. Maximizing the Social Welfare of Virtual Power Players Operation in Case of Excessive Wind Power

    DEFF Research Database (Denmark)

    Faria, Pedro; Vale, Zita; Morais, Hugo

    2013-01-01

    based generation (including wind power) has caused several changes in the operation and planning of power systems and of electricity markets. Sometimes the available non-dispatchable generation is higher than the demand. This generation must be used; otherwise it is wasted if not stored or used...... that aggregates and manages the available energy resources. When facing a situation of excessive non-dispatchable generation, including wind power, real time pricing is applied in order to induce the increase of consumption so that wind curtailment is minimized. This method is especially useful when actual...... in this paper using a real 937-bus distribution network with 20.310 consumers and 548 distributed generators, some of them non-dispatchable and with must take contracts. The implemented scenario corresponds to a real day in Portuguese power system....

  20. Distributed Optimization of Sustainable Power Dispatch and Flexible Consumer Loads for Resilient Power Grid Operations

    Science.gov (United States)

    Srikantha, Pirathayini

    Today's electric grid is rapidly evolving to provision for heterogeneous system components (e.g. intermittent generation, electric vehicles, storage devices, etc.) while catering to diverse consumer power demand patterns. In order to accommodate this changing landscape, the widespread integration of cyber communication with physical components can be witnessed in all tenets of the modern power grid. This ubiquitous connectivity provides an elevated level of awareness and decision-making ability to system operators. Moreover, devices that were typically passive in the traditional grid are now `smarter' as these can respond to remote signals, learn about local conditions and even make their own actuation decisions if necessary. These advantages can be leveraged to reap unprecedented long-term benefits that include sustainable, efficient and economical power grid operations. Furthermore, challenges introduced by emerging trends in the grid such as high penetration of distributed energy sources, rising power demands, deregulations and cyber-security concerns due to vulnerabilities in standard communication protocols can be overcome by tapping onto the active nature of modern power grid components. In this thesis, distributed constructs in optimization and game theory are utilized to design the seamless real-time integration of a large number of heterogeneous power components such as distributed energy sources with highly fluctuating generation capacities and flexible power consumers with varying demand patterns to achieve optimal operations across multiple levels of hierarchy in the power grid. Specifically, advanced data acquisition, cloud analytics (such as prediction), control and storage systems are leveraged to promote sustainable and economical grid operations while ensuring that physical network, generation and consumer comfort requirements are met. Moreover, privacy and security considerations are incorporated into the core of the proposed designs and these

  1. Daya Bay Nuclear Power Station operation and management indicators system

    International Nuclear Information System (INIS)

    Fang Chunfa

    2000-01-01

    Ever since the commercial operation of Daya Bay Nuclear Power Station (GNPS), dynamic objective management concept that features modern enterprises has been adopted by the station to manage all operational activities with the guidance of business plan. And some quantitative indicators have been employed in order to measure effectively the progress status of these operational activities. After several years' evolvement, a hierarchical and standard performance indicators system has been developed and is playing an active part in the plant's efforts towards top quartile of world nuclear power industry. Structured hierarchically with higher levels resolving into lower levels and lower levels committing to higher levels, the indicator system represents the corporate vision, WANO (World Association of Nuclear Operators) performance indicators, plant integrated indicators and departmental key indicators, covering such areas as safety, production, environment, human resource and cost control. The indicator system not only reflects performance-centered management concept, but also shows the controllability of the whole operational process of the station. Indicators of a certain level serve as both early warnings to superior indicators (lagging indicators in this case) and effects to inferior indicators (leading indicators in this case). The dynamic status of these indicators, numbered more than 230, will eventually be fed back to the business plan and realized through daily work of every branch, and even every member of the workforce. With the indicator system as a quantitative management tool, and an effective tracking system, GNPS has achieved great success in self-assessment, objective definition, improvement follow up, resource re-allocation, and management-staff communication. Periodic plant performance assessment is performed through spider chart and other pictorial diagrams. Indicators are displayed at the plant entrance, offices, Main Control Room and SIS network

  2. Research on operation support system for nuclear power plants

    International Nuclear Information System (INIS)

    Wakabayashi, Jiro

    1989-01-01

    Nuclear power plants are the typical, complex, large scale engineering system, and at the time of accidents, there is the possibility to extend disasters to wide range beyond borders, therefore, it is the feature that the requirement for their reliability and safety is much severe as compared with other engineering systems. The fact that human errors become the major cause of large accidents is in common in large scale engineering systems, and the development of the operation support system for preventing it has become an important research subject. Also the research on design support system and maintenance support system is in progress to prevent human errors. Operation support system is composed of diagnostic system, operation guide system, man-machine interface and knowledge data base, and throughout these, the research on the human errors arising in the process of human decision making becomes the basis. Rasmussen's model for decision making, the classification of human errors and the reliability analysis for men, the factors affecting human errors, the acquisition of knowledge, the compilation and management of knowledge data base, the diagnostic system, operation guide system and man-machine interface are described. (K.I.)

  3. Emission operational strategy for combined cooling, heating, and power systems

    International Nuclear Information System (INIS)

    Fumo, Nelson; Mago, Pedro J.; Chamra, Louay M.

    2009-01-01

    Integrated Energy Systems (IES), as technology that use thermal activated components to recover waste heat, are energy systems that offer key solution to global warming and energy security through high overall energy efficiency and better fuel use. Combined Cooling, Heating, and Power (CCHP) Systems are IES that use recovered thermal energy from the prime mover to produce heating and cooling for the building. The CCHP operational strategy is critical and it has to be considered in a well designed system since it defines the ultimate goal for the benefits expected from the system. One of the most common operational strategies is the cost-oriented strategy, which allows the system to operate at the lowest cost. A primary energy strategy (PES) optimizes energy consumption instead of cost. However, as a result of the worldwide concern about global warming, projects that target reduction of greenhouse gas (GHG) emissions have gained a lot of interest. Therefore, for a CCHP system, an emission strategy (ES) would be an operational strategy oriented to minimize emission of pollutants. In this study, the use of an ES is proposed for CCHP systems targeted to reduce emission of pollutants. The primary energy consumption (PEC) reduction and carbon dioxide (CO 2 ) emission reduction obtained using the proposed ES are compared with results obtained from the use of a PES. Results show that lower emission of CO 2 is achieved with the ES when compared with the PES, which prove the advantage of the ES for the design of CCHP systems targeted to emissions reduction.

  4. Self-assessment of operational safety for nuclear power plants

    International Nuclear Information System (INIS)

    1999-12-01

    Self-assessment processes have been continuously developed by nuclear organizations, including nuclear power plants. Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of this process as an effective way for improving safety performance. Self-assessment involves the use of different types of tools and mechanisms to assist the organizations in assessing their own safety performance against given standards. This helps to enhance the understanding of the need for improvements, the feeling of ownership in achieving them and the safety culture as a whole. Although the primary beneficiaries of the self-assessment process are the plant and operating organization, the results of the self-assessments are also used, for example, to increase the confidence of the regulator in the safe operation of an installation, and could be used to assist in meeting obligations under the Convention on Nuclear Safety. Such considerations influence the form of assessment, as well as the type and detail of the results. The concepts developed in this report present the basic approach to self-assessment, taking into consideration experience gained during Operational Safety Review Team (OSART) missions, from organizations and utilities which have successfully implemented parts of a self-assessment programme and from meetings organized to discuss the subject. This report will be used in IAEA sponsored workshops and seminars on operational safety that include the topic of self-assessment

  5. Conceptual design of autonomous operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Endou, A.; Saiki, A.; Miki, T.; Himeno, Y.

    1993-01-01

    Conceptual design of an autonomous operation system for nuclear power plants has been carried out. Prime objective is to grade up operation reliability by eliminating human factors and enhancing control capabilities. For this objective, operators' role and traditional controllers are replaced with artificial intelligence (AI). Norms of autonomy are defined as (a) to maintain its own basic functions, (b) to protect oneself from catastrophic events, (c) to reorganize oneself in case of its partial failure, (d) to harmonize with the environment, and (e) to improve its performance by itself. For the present, a great emphasis is put on realizing humanlike knowledge-based decision-making process by AI in accordance with the norms (a) and (c). To do this, the authors take a model-based approach and it is intended to make modeling of a problem-solving process from multiple viewpoints and structurization of knowledge used in the process. A hierarchical distributed cooperative system configuration is adopted to allow to dynamically reorganize system functions and it is realized by an object-oriented multi-agent system. Plural agents based on different methodology from each other are applied to individual function or methodology diversity is assured to prevent loss of system functions by common cause failure and to reorganize integrant agents. A prototype autonomous operation system is now under development. (orig.)

  6. A study on the Safe Operation of RHRS during Shut-Down and Low Power Operations of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Moon Hun; Sung, Chang Kyung; Kim, Yang Suk; You, Sun Oh; Joo, In Chul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1996-08-01

    The main objective is to perform basic research for safe operation of RHRs, which is an important part in the safety analysis of nuclear reactors during a mid-loop operation of nuclear power plants. To achieve this objective, a series of experiments have been performed to simulate the wave phenomena of countercurrent flow that may occur in the hot legs during a mid-loop operation. The major contents and the scope are as follows, To collect and to analyse existing experimental works and also numerical works which have been carried out using large computer codes. To collect and to analyse existing works on the flow patterns of two-phase flows. To perform a series of experiments to simulate the wave phenomena for the countercurrent two-phase flow in hot legs. To obtain correlations for the interfacial friction factor and the flow patterns for a countercurrent flow from the experimentally measured parameters. To obtain the interfacial friction factor between the two-phases of air-water countercurrent flow in a horizontal pipe, a series of experiments have been performed using two different sections of 0.05 m in diameter, whose lengths are 2 m and 4 m, respectively. The results presented here can be used as the fundamental information to obtain the most important thermal-hydraulic parameters such as flow patterns and interfacial friction factors for air-water two-phase flows, which are necessary for safety analyses and operation of nuclear power plants during a mid-loop operation. 46 refs., 8 tabs., 35 figs., 3 ills. (author)

  7. U.S. Forward Operating Base Applications of Nuclear Power

    International Nuclear Information System (INIS)

    Griffith, George W.

    2015-01-01

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  8. The design of operating procedures manuals for nuclear power plants

    International Nuclear Information System (INIS)

    Bohr, E.; Preuss, W.; Reinartz, G.; Thau, G.

    1977-03-01

    This report describes the findings of a research on the desirable design of operating procedures manuals for nuclear power plants. The work was supported by a grant of the Federal Department of the Interior. Information was acquired from different sources. Interviews and discussions on manual design were carried out with manual users in nuclear power plants. Moreover, tasks carried out using procedures were either observed or, alternatively, the manner of using procedures was elicited by interviews. In addition, manual writers, managers from manufacturers and utilities, nuclear experts, and individuals involved in manual specification activities were interviewed. A major source of information has been the pertinent scientific and technical findings scattered in the literature on topics such as instructional technology, engineering psychology, psycholinguistics, and typography. A comprehensive bibliography is included. General rules are established on designing instructional material for use on the job, aiming at increasing their legability, comprehensibility, and suitability to guide human performance. The application of these rules to the design of individual operating procedures is demonstrated. Recommendations are given on the design, layout, development and implementation of manuals. (orig.) [de

  9. Upgrading the power supplies of TEXTOR for three Tesla operation

    International Nuclear Information System (INIS)

    Giesen, B.; Veiders, E.; Petree, F.; Fink, R.; Wagnitz, R.

    1986-01-01

    The toroidal magnetic system of TEXTOR can tolerate a magnetic field load of up to 2.6 Tesla routinely at full plasma current, and of up to 3 Tesla under certain boundary conditions and for a restricted number of discharges. The original power supply which can generate a toroidal magnetic field of 2 Tesla has been upgraded to operate at a field strength of 3 Tesla, by adding a new, controlled rectifier, with its own independent control, connected in parallel with the first. Studies were undertaken to determine its behaviour where control is lost, such as when a circuit breaker trips or in ''freewheel'' operation. This paper analyzes this asymmetrical arrangement and discusses the danger of damaging the smaller unit by commutating a large current into it. Moreover, in order to improve the availability of TEXTOR, the new controlled rectifier is redundant to two other units that control the vertical field and the ohmic heating coil currents. For this purpose the two bridges of this 12-pulse system are to be changed from a parallel to a series connexion, the free-wheeling diodes are disconnected and redeployed to block the large voltage pulses that are induced at plasma initiation, and 3-phase ''freewheeling'' thyristors are added that serve to reduce reactive power consumption

  10. Evaluating and improving nuclear power plant operating performance

    International Nuclear Information System (INIS)

    1999-07-01

    This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world's most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America

  11. Evaluating and improving nuclear power plant operating performance

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world`s most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America Figs, tabs

  12. CEA contribution to power plant operation with high burnup level

    International Nuclear Information System (INIS)

    1981-03-01

    High level burnup in PWR leads to investigate again the choices carried out in the field of fuel management. French CEA has studied the economic importance of reshuffling technique, cycle length, discharge burnup, and non-operation period between two cycles. Power plants operators wish to work with increased length cycles of 18 months instead of 12. That leads to control problems because the core reactivity cannot be controlled with the only soluble boron: moderator temperature coefficient must be negative. With such cycles, it is necessary to use burnable poisons and for economic reasons with a low penalty in end of cycle. CEA has studied the use of Gd 2 O 3 mixed with fuel or with inert element like Al 2 O 3 . Parametric studies of specific weights, efficacities relatively to the fuel burnup and the fuel enrichment have been carried out. Particular studies of 1 month cycles with Gd 2 O 3 have shown the possibility to control power distribution with a very low reactivity penalty in EOC. In the same time, in the 100 MW PWR-CAP, control reactivity has been made with large use of gadolinia in parallel with soluble boron for the two first cycles

  13. Risk contribution from low power, shutdown, and other operational modes beyond full power

    Energy Technology Data Exchange (ETDEWEB)

    Whitehead, D.W.; Brown, T.D. [Sandia National Labs., Albuquerque, NM (United States); Chu, T.L. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1995-04-01

    During 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 (a pressurized water reactor) and Grand Gulf (a boiling water reactor), were selected for study by Brookhaven National Laboratory and Sandia National Laboratories, respectively. The program objectives included assessing the risks of severe accidents initiated during plant operational states other than full power and comparing estimated core damage frequencies, important accident sequences, and other qualitative and quantitative results with full power accidents as assessed in NUREG-1150. The scope included a Level 3 probabilistic risk assessment (PRA) for traditional internal events and a Level 1 PRA on fire, flooding, and seismically induced core damage sequences. A phased approach was used in Level 1. In Phase 1 the concept of plant operational states (POSs) was developed to provide a better representation of the plant as it transitions from power to nonpower operation. This included a coarse screening analysis of all POSs to identify vulnerable plant configurations, to characterize (on a high, medium, or low basis) potential frequencies of core damage accidents, and to provide a foundation for a detailed Phase 2 analysis. In Phase 2, selected POSs from both Grand Gulf and Surry were chosen for detailed analysis. For Grand Gulf, POS 5 (approximately cold shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage was selected. For Surry, three POSs representing the time the plant spends in midloop operation were chosen for analysis. These included POS 6 and POS 10 of a refueling outage and POS 6 of a drained maintenance outage. Level 1 and Level 2/3 results from both the Surry and Grand Gulf analyses are presented.

  14. Risk contribution from low power, shutdown, and other operational modes beyond full power

    International Nuclear Information System (INIS)

    Whitehead, D.W.; Brown, T.D.; Chu, T.L.; Pratt, W.T.

    1995-01-01

    During 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 (a pressurized water reactor) and Grand Gulf (a boiling water reactor), were selected for study by Brookhaven National Laboratory and Sandia National Laboratories, respectively. The program objectives included assessing the risks of severe accidents initiated during plant operational states other than full power and comparing estimated core damage frequencies, important accident sequences, and other qualitative and quantitative results with full power accidents as assessed in NUREG-1150. The scope included a Level 3 probabilistic risk assessment (PRA) for traditional internal events and a Level 1 PRA on fire, flooding, and seismically induced core damage sequences. A phased approach was used in Level 1. In Phase 1 the concept of plant operational states (POSs) was developed to provide a better representation of the plant as it transitions from power to nonpower operation. This included a coarse screening analysis of all POSs to identify vulnerable plant configurations, to characterize (on a high, medium, or low basis) potential frequencies of core damage accidents, and to provide a foundation for a detailed Phase 2 analysis. In Phase 2, selected POSs from both Grand Gulf and Surry were chosen for detailed analysis. For Grand Gulf, POS 5 (approximately cold shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage was selected. For Surry, three POSs representing the time the plant spends in midloop operation were chosen for analysis. These included POS 6 and POS 10 of a refueling outage and POS 6 of a drained maintenance outage. Level 1 and Level 2/3 results from both the Surry and Grand Gulf analyses are presented

  15. Lower bound on the spectrum of the Schr\\"odinger operator in the plane with delta-potential supported by a curve

    OpenAIRE

    Lobanov, Igor; Lotoreichik, Vladimir; Popov, Igor

    2009-01-01

    We consider the Schr\\"odinger operator in the plane with delta-potential supported by a curve. For the cases of an infinite curve and a finite loop we give estimates on the lower bound of the spectrum expressed explicitly through the strength of the interaction and a parameter which characterizes geometry of the curve. Going further we cut the curve into finite number of pieces and estimate the bottom of the spectrum using the parameters for the pieces. As an application of the elaborated the...

  16. Intelligent engineering and technology for nuclear power plant operation

    International Nuclear Information System (INIS)

    Wang, P.P.; Gu, X.

    1996-01-01

    The Three-Mile-Island accident has drawn considerable attention by the engineering, scientific, management, financial, and political communities as well as society at large. This paper surveys possible causes of the accident studied by various groups. Research continues in this area with many projects aimed at specifically improving the performance and operation of a nuclear power plant using the contemporary technologies available. In addition to the known cause of the accident and suggest a strategy for coping with these problems in the future. With the increased use of intelligent methodologies called computational intelligence or soft-computing, a substantially larger collection of powerful tools are now available for our designers to use in order to tackle these sensitive and difficult issues. These intelligent methodologies consists of fuzzy logic, genetic algorithms, neural networks, artificial intelligence and expert systems, pattern recognition, machine intelligence, and fuzzy constraint networks. Using the Three-Mile-Island experience, this paper offers a set of specific recommendations for future designers to take advantage of the powerful tools of intelligent technologies that we are now able to master and encourages the adoption of a novel methodology called fuzzy constraint network

  17. Operating experience from Swedish nuclear power plants, 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    From a safety point of view, 2000 was - as were previous years - satisfactory. Total electricity production from the Swedish nuclear power stations amounted to 54.2 TWh, which was over 20% less than the 70.2 TWh produced in 1999. The two main reasons for the reduction were the closure of Barsebaeck 1 on 1st December 1999, and the cutback in output from all reactors due to the particularly good availability of hydro power in 2000. Some reactors were even shut down completely as a result of the low power demand, which has not happened previously. The quantity of unutilised production capacity as a result of these reductions amounted to 11.6 TWh. Costdown operation prior to the annual overhaul shutdowns, which makes better use of the fuel, represented a further 2.1 TWh of unutilised capacity. The average energy availability of the three PWRs at Ringhals was 82.0%, while that of the eight BWRs was 84.2%. Forsmark 3, Ringhals 3 and Oskarshamn 3 all had average availabilities of over 90%. Of five events with safety implications that occurred in the plants during the year, three are described under Special Reporting. One of them relates to the crack indications in welds that were found in an American PWR in the autumn, and which were subsequently also found in Ringhals 4.

  18. Operating experience from Swedish nuclear power plants, 2000

    International Nuclear Information System (INIS)

    2001-01-01

    From a safety point of view, 2000 was - as were previous years - satisfactory. Total electricity production from the Swedish nuclear power stations amounted to 54.2 TWh, which was over 20% less than the 70.2 TWh produced in 1999. The two main reasons for the reduction were the closure of Barsebaeck 1 on 1st December 1999, and the cutback in output from all reactors due to the particularly good availability of hydro power in 2000. Some reactors were even shut down completely as a result of the low power demand, which has not happened previously. The quantity of unutilised production capacity as a result of these reductions amounted to 11.6 TWh. Costdown operation prior to the annual overhaul shutdowns, which makes better use of the fuel, represented a further 2.1 TWh of unutilised capacity. The average energy availability of the three PWRs at Ringhals was 82.0%, while that of the eight BWRs was 84.2%. Forsmark 3, Ringhals 3 and Oskarshamn 3 all had average availabilities of over 90%. Of five events with safety implications that occurred in the plants during the year, three are described under Special Reporting. One of them relates to the crack indications in welds that were found in an American PWR in the autumn, and which were subsequently also found in Ringhals 4

  19. Microwave Power Beaming Infrastructure for Manned Lightcraft Operations: Part 2

    International Nuclear Information System (INIS)

    Myrabo, Leik N.

    2008-01-01

    In the past ∼7 years, microwave gyrotron technology has rapidly evolved to a critical threshold wherein ultra-energetic space launch missions based on beamed energy propulsion (BEP) now appear eminently feasible. Over the next 20 years, hundred megawatt-class microwave power-beaming stations could be prototyped on high deserts and 3- to 4 km mountain peaks before migrating into low Earth orbit, along with their passive microwave relay satellites. Described herein is a 20 GW rechargeable nuclear power satellite and microwave power-beaming infrastructure designed for manned space launch operations in the year 2025. The technological readiness of 2500 GJ superconducting magnetic energy storage 'batteries', 433-m ultralight space structures, 100 MW liquid droplet radiators, 1-6+ MW gyrotron sources, and mega-scale arrays (e.g., 3000 phase-locked units) is addressed. Microwave BEP is 'breakthrough' technology with the very real potential to radically reduce space access costs by factors of 100 to 1000 in the forseeable future

  20. Requirements and operation of decentralised power plants in the changing power market

    International Nuclear Information System (INIS)

    Hoenings, Norbert; Hornig, Niels; Steinbach, Sebastian

    2014-01-01

    E.ON plans and realises distributed industrial power plants on the basis of contracting schemes. Target is to reduce energy costs without investment by the customer himself. Gas turbine CHP plants are very flexible and offer many possibilities for the operator to adjust optimally to a constantly changing energy market. This aspect is becoming increasingly important due to the increasing share of renewables. However, the economic situation for CHP plants has deteriorated significantly, due to the current market situation distorted by the subsidised renewable power generation. (orig.)