Nuclear Power Plant Simulation Game.

Science.gov (United States)

Weiss, Fran

1979-01-01

Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

Simulation model of a PWR power plant

International Nuclear Information System (INIS)

Larsen, N.

1987-03-01

A simulation model of a hypothetical PWR power plant is described. A large number of disturbances and failures in plant function can be simulated. The model is written as seven modules to the modular simulation system for continuous processes DYSIM and serves also as a user example of this system. The model runs in Fortran 77 on the IBM-PC-AT. (author)

The innovative simulator for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kurosawa, A [The Inst. of Applied Energy, Tokyo (Japan); Ohashi, H; Akiyama, M [Univ. of Tokyo (Japan). Dept. of Nuclear Engineering

1994-12-31

Nuclear power simulators are becoming more and more important tools for ensuring the safety and the reliability during the whole cycle of plants from design to operation. Recently, there has been remarkable progress in computer science such as increase of computing speed, refinement of mathematical models and emergence of various AI technologies. By fully exploiting this progress to nuclear plant simulators, it becomes possible to achieve much faster, more extensive and more realistic simulation than ever. The Institute of Applied Energy (IAE) has organized a feasibility study on the advanced simulator since 1990, to develop the concept of nuclear power plant simulators in future. In this study, several academic organizations make fundamental researches on parallelization of transient analyses, large-scale parallel computing, thermal-hydraulic analysis using cellular automata, code development methodology by module-integration and task scheduling methods for parallel compilers. The concept and impact of the innovative simulator, as a multipurpose simulator complex, are summarized from the viewpoints of wide range scenarios including severe accidents, 3D multi-media interface, much faster than real-time simulation, and innovative algorithms for analyses of thermal-hydraulics, structure, neutronkinetics and their coupled phenomena. (orig.) (2 refs., 2 figs.).

The innovative simulator for nuclear power plants

International Nuclear Information System (INIS)

Kurosawa, A.; Ohashi, H.; Akiyama, M.

1994-01-01

Nuclear power simulators are becoming more and more important tools for ensuring the safety and the reliability during the whole cycle of plants from design to operation. Recently, there has been remarkable progress in computer science such as increase of computing speed, refinement of mathematical models and emergence of various AI technologies. By fully exploiting this progress to nuclear plant simulators, it becomes possible to achieve much faster, more extensive and more realistic simulation than ever. The Institute of Applied Energy (IAE) has organized a feasibility study on the advanced simulator since 1990, to develop the concept of nuclear power plant simulators in future. In this study, several academic organizations make fundamental researches on parallelization of transient analyses, large-scale parallel computing, thermal-hydraulic analysis using cellular automata, code development methodology by module-integration and task scheduling methods for parallel compilers. The concept and impact of the innovative simulator, as a multipurpose simulator complex, are summarized from the viewpoints of wide range scenarios including severe accidents, 3D multi-media interface, much faster than real-time simulation, and innovative algorithms for analyses of thermal-hydraulics, structure, neutronkinetics and their coupled phenomena. (orig.) (2 refs., 2 figs.)

A landscape simulation system for power plants

International Nuclear Information System (INIS)

Yoshinaga, Toshiaki; Yoshida, Miki; Usami, Yoshiaki.

1997-01-01

As scenes of power plants give many influences to environments, the plants that harmonized with the environments are demanded. We developed a landscape simulation system for the plants by using computer graphics technologies. This system has functions to generate realistic images about plant buildings and environments. Since the system contains information of ridge lines in addition to usual terrain data, the terrain shapes are expressed more precisely. Because the system enables users to visualize plant construction plans, the advance evaluations of plant scenes become possible. We regard this system as useful for environmental assessment of power plants. (author)

AEP smart grid demo : virtual power plant simulation

International Nuclear Information System (INIS)

Riggins, M.

2010-01-01

This power point presentation described a virtual power plant simulation study conducted by American Electric Power (AEP), a utility with over 5.4 million customers. The simulation study was conducted in order to enable the installation of smart meters as well as to ensure remote monitoring and control of distribution line devices and energy resources. The simulation study assessed the functionality and performance of a fully integrated smart grid using real system and device information and data. The simulations were also used to optimize power costs and plant efficiency. Energy resources simulated in the study included battery installations, photovoltaic (PV) systems, natural gas-fired reciprocating engines, hybrid electric vehicles, community energy storage systems, and wind turbines. The study also assessed the regional market structure. The impacts of various protocols and standards were assessed in order to determine control system requirement and evaluate constraints and energy efficiency targets. The simulation included regional power system, station transformers, and distribution circuit breakers. Various automation schemes were considered, as well as an integrated VAR control concept. Community energy storage unit specifications were also discussed. tabs., figs.

Solar thermal power plants simulation using the TRNSYS software

Energy Technology Data Exchange (ETDEWEB)

Popel, O.S.; Frid, S.E.; Shpilrain, E.E. [Institute for High Temperatures, Russian Academy of Sciences (IVTAN), Moscow (Russian Federation)

1999-03-01

The paper describes activity directed on the TRNSYS software application for mathematical simulation of solar thermal power plants. First stage of developments has been devoted to simulation and thermodynamic analysis of the Hybrid Solar-Fuel Thermal Power Plants (HSFTPP) with gas turbine installations. Three schemes of HSFTPP, namely: Gas Turbine Regenerative Cycle, Brayton Cycle with Steam Injection and Combined Brayton-Rankine Cycle,- have been assembled and tested under the TRNSYS. For this purpose 18 new models of the schemes components (gas and steam turbines, compressor, heat-exchangers, steam generator, solar receiver, condenser, controllers, etc) have been elaborated and incorporated into the TRNSYS library of 'standard' components. The authors do expect that this initiative and received results will stimulate experts involved in the mathematical simulation of solar thermal power plants to join the described activity to contribute to acceleration of development and expansion of 'Solar Thermal Power Plants' branch of the TRNSYS. The proposed approach could provide an appropriate basis for standardization of analysis, models and assumptions for well-founded comparison of different schemes of advanced solar power plants. (authors)

NUCLEBRAS' experience in the implantation of a nuclear power plants simulator

International Nuclear Information System (INIS)

Spitalnik, J.; Fonseca, G.

1985-01-01

The experiences gained by NUCLEBRAS in the setting up of a Nuclear Power Plant Simulator Training Center, cover the design and manufacture of the simulator for the Angra-2 type nuclear power plants, the training of the simulator operation and maintenance personnel, in preparation for the training of the Brazilian nuclear power plant operators, the development of the simulator training programs and materials, the temporary installation and utilization of the simulator in the FRG, including the training of operators of the Trillo nuclear power plant, in Spain. The simulator shall be finally installed in Brazil, at the vicinity of the Angra-2 site, in 1985, when it is foreseen to start the training of the Angra-2 operators. (Author) [pt

Compact simulators for WWER-440 type nuclear power plants

International Nuclear Information System (INIS)

Vegh, E.; Janosy, J.S.

1991-09-01

This paper describes a compact simulator for VVER-440 type plants. Up till now three simulators have been delivered: to Paks Nuclear Power Plant (Hungary), and to Kola and Rovno NPPs (Soviet Union). In this compact simulator the modelling complexity of the plant is almost similar to that of a full-scope one apart from the Control Room being replaced by a Control Desk and four colour graphic display units. The simulation of the plant covers the whole operating range: from cold shut-down state to nominal power level. The simulator contains up to 32 different initial conditions. Moreover, every 5 minutes the simulator produces so called 'snapshots', i.e. disc images of the Data Base. Using these snapshots the instructor can go back in time (called backtracking) in order to repeat some previously passed events

Open Source Power Plant Simulator Development Under Matlab Environment

International Nuclear Information System (INIS)

Ratemi, W.M.; Fadilah, S.M.; Abonoor, N

2008-01-01

In this paper an open source programming approach is targeted for the development of power plant simulator under Matlab environment. With this approach many individuals can contribute to the development of the simulator by developing different orders of complexities of the power plant components. Such modules can be modeled based on physical principles, or using neural networks or other methods. All of these modules are categorized in Matlab library, of which the user can select and build up his simulator. Many international companies developed its own authoring tool for the development of its simulators, and hence it became its own property available for high costs. Matlab is a general software developed by mathworks that can be used with its toolkits as the authoring tool for the development of components by different individuals, and through the appropriate coordination, different plant simulators, nuclear, traditional , or even research reactors can be computerly assembled. In this paper, power plant components such as a pressurizer, a reactor, a steam generator, a turbine, a condenser, a feedwater heater, a valve, a pump are modeled based on physical principles. Also a prototype modeling of a reactor ( a scram case) based on neural networks is developed. These modules are inserted in two different Matlab libraries one called physical and the other is called neural. Furthermore, during the simulation one can pause and shuffle the modules selected from the two libraries and then proceed the simulation. Also, under the Matlab environment a PID controller is developed for multi-loop plant which can be integrated for the control of the appropriate developed simulator. This paper is an attempt to base the open source approach for the development of power plant simulators or even research reactor simulators. It then requires the coordination among interested individuals or institutions to set it to professionalism. (author)

Nuclear power plant diagnostics study at the Midland training simulator

International Nuclear Information System (INIS)

Reifman, J.; Rank, P.; Lee, J.C.

1991-01-01

Training simulators provide a real world environment for testing advanced diagnostic and control systems as an aid to nuclear power plant operators. The simulators not only duplicate the hardware din the actual control room, allowing for analysis of man-machine interface, but also represent the dynamic behavior of the reference plant in real-time, in a realistic manner. Training simulators provide the means to representing the reference plant operations in a wide range of operation conditions including off-normal and emergency conditions. Transient events with very low probability of occurrence can then be represented and used to test the capabilities of advanced diagnostic and control systems. For these reasons, full-scope operator training simulators have been used as a test bed for a number of advanced diagnostic concepts. The University of Michigan and Consumers Power Company have been collaborating in a program devoted to the development and study of advanced concepts for automatic diagnostics and control of nuclear power plants. The program has been focused on the use of the full-scope operator training Midland Nuclear Power Plant Unit 2 (MNP-2) Simulator for development, testing, and verification of advanced diagnostics concepts. In their current efforts, the authors have developed two artificial intelligent (AI) diagnostic concepts that have been applied to the MNP-2 Simulator: the systematic generation and updating of a rule-based knowledge system for nuclear power plant diagnostics and a nonlinear parameter estimation algorithm called the simulation filter. The simulation filter algorithm is used with the MNP-2 Simulator to improve the simulation of the Three Mile Island Unit 2 (TMI-2) accident. 11 refs., 4 figs

Modelling and Simulation of VSC-HVDC Connection for Wind Power Plants

DEFF Research Database (Denmark)

Chaudhary, Sanjay Kumar; Teodorescu, Remus; Rodriguez, Pedro

2009-01-01

This paper describes the modelling and simulation of offshore wind power plants (WPP) connected to the onshore power system grid by VSC based HVDC transmission. Offshore wind power plant is modelled with several wind turbine generators connected to two separate collector buses with their own plant...... wind turbines. Simulation of power ramping up and down as well as steady state operation has been demonstrated. As an additional case, the primary reserve control logic has been implemented and simulated in PSCAD model....

Current experience with nuclear power plant simulators and analysers

International Nuclear Information System (INIS)

Drozd, A.

1998-01-01

Topics of a Specialist Meeting are presented on Simulators and Plant Analyzers: Current Issues in Nuclear Power Plant Simulation (Espoo, Finland). They dealt with the need for maintaining expertise, training and education, control rooms and operator support tools, simulators as tools for plant safety analysis. The major conclusions of the payers and the meeting are discussed. (R.P.)

Simulation Based Data Reconciliation for Monitoring Power Plant Efficiency

International Nuclear Information System (INIS)

Park, Sang Jun; Heo, Gyun Young

2010-01-01

Power plant efficiency is analyzed by using measured values, mass/energy balance principles, and several correlations. Since the measured values can have uncertainty depending on the accuracy of instrumentation, the results of plant efficiency should definitely have uncertainty. The certainty may occur due to either the randomness or the malfunctions of a process. In order to improve the accuracy of efficiency analysis, the data reconciliation (DR) is expected as a good candidate because the mathematical algorithm of the DR is based on the first principles such as mass and energy balance considering the uncertainty of instrumentation. It should be noted that the mass and energy balance model for analyzing power plant efficiency is equivalent to a steady-state simulation of a plant system. Therefore the DR for efficiency analysis necessitates the simulation which can deal with the uncertainty of instrumentation. This study will propose the algorithm of the simulation based DR which is applicable to power plant efficiency monitoring

Application of Nuclear Power Plant Simulator for High School Student Training

Energy Technology Data Exchange (ETDEWEB)

Kong, Chi Dong; Choi, Soo Young; Park, Min Young; Lee, Duck Jung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2014-10-15

In this context, two lectures on nuclear power plant simulator and practical training were provided to high school students in 2014. The education contents were composed of two parts: the micro-physics simulator and the macro-physics simulator. The micro-physics simulator treats only in-core phenomena, whereas the macro-physics simulator describes whole system of a nuclear power plant but it considers a reactor core as a point. The high school students showed strong interests caused by the fact that they operated the simulation by themselves. This abstract reports the training detail and evaluation of the effectiveness of the training. Lectures on nuclear power plant simulator and practical exercises were performed at Ulsan Energy High School and Ulsan Meister High School. Two simulators were used: the macro- and micro-physics simulator. Using the macro-physics simulator, the following five simulations were performed: reactor power increase/decrease, reactor trip, single reactor coolant pump trip, large break loss of coolant accident, and station black-out with D.C. power loss. Using the micro-physics simulator, the following three analyses were performed: the transient analysis, fuel rod performance analysis, and thermal-hydraulics analysis. The students at both high schools showed interest and strong support for the simulator-based training. After the training, the students showed passionate responses that the education was of help for them to get interest in a nuclear power plant.

Application of Nuclear Power Plant Simulator for High School Student Training

International Nuclear Information System (INIS)

Kong, Chi Dong; Choi, Soo Young; Park, Min Young; Lee, Duck Jung

2014-01-01

In this context, two lectures on nuclear power plant simulator and practical training were provided to high school students in 2014. The education contents were composed of two parts: the micro-physics simulator and the macro-physics simulator. The micro-physics simulator treats only in-core phenomena, whereas the macro-physics simulator describes whole system of a nuclear power plant but it considers a reactor core as a point. The high school students showed strong interests caused by the fact that they operated the simulation by themselves. This abstract reports the training detail and evaluation of the effectiveness of the training. Lectures on nuclear power plant simulator and practical exercises were performed at Ulsan Energy High School and Ulsan Meister High School. Two simulators were used: the macro- and micro-physics simulator. Using the macro-physics simulator, the following five simulations were performed: reactor power increase/decrease, reactor trip, single reactor coolant pump trip, large break loss of coolant accident, and station black-out with D.C. power loss. Using the micro-physics simulator, the following three analyses were performed: the transient analysis, fuel rod performance analysis, and thermal-hydraulics analysis. The students at both high schools showed interest and strong support for the simulator-based training. After the training, the students showed passionate responses that the education was of help for them to get interest in a nuclear power plant

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.

Simulators for training nuclear power plant personnel

International Nuclear Information System (INIS)

1993-01-01

Simulator training and retraining of operations personnel is essential for their acquiring the necessary knowledge, skills and qualification for operating a nuclear power plant, and for effective feedback of experience including human based operating errors. Simulator training is the most effective way by far of training operations personnel in co-operation and communication in a team, which also involves instilling attitudes and approaches for achieving excellence and individual responsibility and alertness. This technical document provides guidance to Member States on the procurement, setting up and utilization of a simulator training centre; it will also be useful for organizations with previous experience in the use of simulators for training. The document is the result of a series of advisory and consultants meetings held in the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation in 1989-1992. 17 refs, 2 tabs

Part-task simulator for a WWER-440 nuclear power plant subsystem

International Nuclear Information System (INIS)

Szabo, B.K.

1988-07-01

PC-based part-task simulators for simulating subsystems of nuclear power plants are low cost tools for operator training. In the Central Research Institute for Physics, Budapest, a simulator system has been developed to facilitate fast development of such simulators. The first application simulates the Neutron Flux Monitoring System of WWER-440 nuclear power plants. (author) 9 refs.; 2 figs

Nuclear power plant training simulator system and method

International Nuclear Information System (INIS)

Ferguson, R.W.; Converse, R.E. Jr.

1975-01-01

A system is described for simulating the real-time dynamic operation of a full scope nuclear powered electrical generating plant for operator training utilizing apparatus that includes a control console with plant component control devices and indicating devices for monitoring plant operation. A general purpose digital computer calculates the dynamic simulation data for operating the indicating devices in accordance with the operation of the control devices. The functions for synchronization and calculation are arranged in a priority structure so as to insure an execution order that provides a maximum overlap of data exchange and simulation calculations. (Official Gazette)

Simulator of nuclear power plant with WWER-440 units

International Nuclear Information System (INIS)

Krcek, V.

1985-01-01

The use is discussed of simulators in the training of qualified personnel for the construction and operation of nuclear power plants. Simulators are used for training all activities and thinking processes related to the control of a nuclear reactor in the course of quasi-steady and non-steady states. The development and implementation is summed up of the construction of such a simulator for WWER-440 nuclear power plants. The main parts of the simulator include the unit control room, the computer system, the teacher's workplace and the interface system. The possibility of simulating the functions of the unit for personnel training is based on the description of the behaviour of the simulated object in form of mathematical models of its basic technological subsystems and their interrelations within the range of operating patterns. (J.C.)

Nuclear power plant diagnostics study at the Midland Training Simulator

International Nuclear Information System (INIS)

Reifman, J.; Rank, P.; Lee, J.C.; Wehe, D.K.

1991-01-01

This paper discusses the implementation of two advanced diagnostic concepts for nuclear power plant diagnostics, the systematic generation and updating of a rule-based system and the simulation filter, at the Midland Nuclear Power Plant Unit 2 Training Simulator. The authors use an entropy minimax pattern recognition algorithm for the systematic construction of the diagnostic rule base. By extracting information from a transient database constructed with the Midland Simulator, the algorithm searches for trends in plant parameters, forming patterns or rules that describe the behavior of the transients. The rules are updated in an incremental manner within the context of the entropy minimax algorithm. The simulation filter is a nonlinear parameter estimation algorithm based on the extended Kalman filter. The authors use the simulation filter to improve the results of crude simulation models by optimally estimating system states given a set of measurements and results from a nonlinear simulation program. The Midland Simulator results of the Three Mile Island accident are significantly improved with the use of the simulation filter

Nuclear power plant simulation on the AD10

International Nuclear Information System (INIS)

Wulff, W.; Cheng, H.S.; Mallen, A.N.; Stritar, A.

1985-01-01

A combination of advanced modeling techniques and the modern, special-purpose peripheral minicomputer AD10 is presented which affords realistic predictions of plant transient and severe off-normal events in LWR power plants through on-line simulations at a speed ten times greater than actual process speeds. Results are shown for a BWR plant simulation. The mathematical models account for nonequilibrium, nonhomogeneous two-phase flow effects in the coolant, for acoustical effects in the steam line and for the dynamics of the recirculation loop and feedwater train. Point kinetics incorporate reactivity feedback for void fraction, for fuel temperature, for coolant temperature, and for boron concentration. Control systems and trip logic are simulated for the nuclear steam supply system. 4 refs., 3 figs

Level-one modules library for DSNP: Dynamic Simulator for Nuclear Power-plants

International Nuclear Information System (INIS)

Saphier, D.

1978-09-01

The Dynamic Simulator for Nuclear Power-plants (DSNP) is a system of programs and data sets by which a nuclear power plant or part thereof can be simulated at different levels of sophistication. The acronym DSNP is used interchangeably for the DSNP language, for the DSNP precompiler, for the DSNP libraries, and for the DSNP document generator. The DSNP language is a set of simple block oriented statements, which together with the appropriate data, comprise a simulation of a nuclear power plant. The majority of the DSNP statements will result in the inclusion of a simulated physical module into the program. FORTRAN statements can be inserted with no restrictions among DSNP statements

Simulation and parametric optimisation of thermal power plant cycles

Directory of Open Access Journals (Sweden)

P. Ravindra Kumar

2016-09-01

Full Text Available The objective of the paper is to analyse parametric studies and optimum steam extraction pressures of three different (subcritical, supercritical and ultra-supercritical coal fired power plant cycles at a particular main steam temperature of 600 °C by keeping the reheat temperature at 537 °C and condenser pressure at 0.09 bar as constant. In order to maximize the heat rate gain possible with supercritical and ultra-supercritical steam conditions, eight stages of feed water heater arrangement with single reheater is considered. The system is optimized in such a way that the percentage exergetic losses are reduced for the increase of the exergetic efficiency and higher fuel utilization. The plant cycles are simulated and optimized by using Cycle Tempo 5.0 simulation software tool. From the simulation study, it is observed that the thermal efficiency of the three different power plant cycles obtained as 41.40, 42.48 and 43.03%, respectively. The specific coal consumption for three different power plant cycles are 0.56, 0.55 and 0.54 Tonnes/MWh. The improvement in feed water temperatures at the inlet of steam generator of respective cycles are 291, 305 and 316 °C.

Common modelling approaches for training simulators for nuclear power plants

International Nuclear Information System (INIS)

1990-02-01

Training simulators for nuclear power plant operating staff have gained increasing importance over the last twenty years. One of the recommendations of the 1983 IAEA Specialists' Meeting on Nuclear Power Plant Training Simulators in Helsinki was to organize a Co-ordinated Research Programme (CRP) on some aspects of training simulators. The goal statement was: ''To establish and maintain a common approach to modelling for nuclear training simulators based on defined training requirements''. Before adapting this goal statement, the participants considered many alternatives for defining the common aspects of training simulator models, such as the programming language used, the nature of the simulator computer system, the size of the simulation computers, the scope of simulation. The participants agreed that it was the training requirements that defined the need for a simulator, the scope of models and hence the type of computer complex that was required, the criteria for fidelity and verification, and was therefore the most appropriate basis for the commonality of modelling approaches. It should be noted that the Co-ordinated Research Programme was restricted, for a variety of reasons, to consider only a few aspects of training simulators. This report reflects these limitations, and covers only the topics considered within the scope of the programme. The information in this document is intended as an aid for operating organizations to identify possible modelling approaches for training simulators for nuclear power plants. 33 refs

Power plant simulation: Experience and perspectives

Energy Technology Data Exchange (ETDEWEB)

Barabino, M; Durando, S [Bailey Esacontrol SpA, Genoa (Italy)

1991-04-01

In the recent years, a growing number of thermal power plants have been equipped with digital distributed control systems (DCS). This paper, following a brief introduction to the architecture of a DCS, points out how the simulation techniques can be integrated within a DCS, allowing either the building up of training simulators or giving the operator adequate help. The issue describes a new concept in the architecture of 'real time' training simulators developed by ENEL (Italian National Electricity Board) and Krupp Atlas Elektronik, together with Bailey Esacontrol for the Piacenza and Port Kelang (Malaysia) training centres. New developments and new architectures are considered for the integration of the control system with process simulation, aimed at global automation and optimization of industrial processes.

Object-oriented simulator of the dynamics of Embalse nuclear power plant

International Nuclear Information System (INIS)

Boroni, Gustavo A.; Cuadrado, M.; Clausse, Alejandro

2000-01-01

LUDWIG is an object-oriented simulator of the dynamics of the CANDU Nuclear power plant Embalse Rio Tercero. The tool consists in a numerical plant analyzer by means of a model of the plant dynamics during normal operation, and a graphic environment for configuration and visualization of results. The simulator was validated against plant transients occurred in the plant and recorded in the past. (author)

Nuclear power plant training simulator fidelity assessment

International Nuclear Information System (INIS)

Carter, R.J.; Laughery, K.R.

1985-01-01

The fidelity assessment portion of a methodology for evaluating nuclear power plant simulation facilities in regard to their appropriateness for conducting the Nuclear Regulatory Commission's operating test was described. The need for fidelity assessment, data sources, and fidelity data to be collected are addressed. Fidelity data recording, collection, and analysis are discussed. The processes for drawing conclusions from the fidelity assessment and evaluating the adequacy of the simulator control-room layout were presented. 3 refs

Simulation study of a system for diagnosis of nuclear power plant operation

International Nuclear Information System (INIS)

Wakabayashi, J.; Fukumoto, A.

1981-01-01

A diagnostic system of the nuclear power plant operation is proposed and the applicability of this system to the actual plant has been verified by computer simulation. A typical pressurized water reactor plant simulator was made by an analog computer and the diagnostic system was made by a digital computer. The observed signals obtained from the actual plant are simulated by superposing the equivalent observation noises generated by the digital computer on the sampled signals obtained from the plant simulator. 8 refs

Estimation of reliability on digital plant protection system in nuclear power plants using fault simulation with self-checking

International Nuclear Information System (INIS)

Lee, Jun Seok; Kim, Suk Joon; Seong, Poong Hyun

2004-01-01

Safety-critical digital systems in nuclear power plants require high design reliability. Reliable software design and accurate prediction methods for the system reliability are important problems. In the reliability analysis, the error detection coverage of the system is one of the crucial factors, however, it is difficult to evaluate the error detection coverage of digital instrumentation and control system in nuclear power plants due to complexity of the system. To evaluate the error detection coverage for high efficiency and low cost, the simulation based fault injections with self checking are needed for digital instrumentation and control system in nuclear power plants. The target system is local coincidence logic in digital plant protection system and a simplified software modeling for this target system is used in this work. C++ based hardware description of micro computer simulator system is used to evaluate the error detection coverage of the system. From the simulation result, it is possible to estimate the error detection coverage of digital plant protection system in nuclear power plants using simulation based fault injection method with self checking. (author)

A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION

Energy Technology Data Exchange (ETDEWEB)

Mike Bockelie; Dave Swensen; Martin Denison; Adel Sarofim; Connie Senior

2004-12-22

In this report is described the work effort to develop and demonstrate a software framework to support advanced process simulations to evaluate the performance of advanced power systems. Integrated into the framework are a broad range of models, analysis tools, and visualization methods that can be used for the plant evaluation. The framework provides a tightly integrated problem-solving environment, with plug-and-play functionality, and includes a hierarchy of models, ranging from fast running process models to detailed reacting CFD models. The framework places no inherent limitations on the type of physics that can be modeled, numerical techniques, or programming languages used to implement the equipment models, or the type or amount of data that can be exchanged between models. Tools are provided to analyze simulation results at multiple levels of detail, ranging from simple tabular outputs to advanced solution visualization methods. All models and tools communicate in a seamless manner. The framework can be coupled to other software frameworks that provide different modeling capabilities. Three software frameworks were developed during the course of the project. The first framework focused on simulating the performance of the DOE Low Emissions Boiler System Proof of Concept facility, an advanced pulverized-coal combustion-based power plant. The second framework targeted simulating the performance of an Integrated coal Gasification Combined Cycle - Fuel Cell Turbine (IGCC-FCT) plant configuration. The coal gasifier models included both CFD and process models for the commercially dominant systems. Interfacing models to the framework was performed using VES-Open, and tests were performed to demonstrate interfacing CAPE-Open compliant models to the framework. The IGCC-FCT framework was subsequently extended to support Virtual Engineering concepts in which plant configurations can be constructed and interrogated in a three-dimensional, user-centered, interactive

Power plant simulation

Energy Technology Data Exchange (ETDEWEB)

Hacking, D [Marconi Simulation (United Kingdom)

1992-09-01

Over many years in the field of simulation Marconi has developed and adopted a number of procedures and methodologies for the management, design and development of an extensive range of training equipment. This equipment encompasses desktop computer-based training systems, generic training devices. The procurement of a training simulator is clearly dictated by the perceived training requirement or problem. Also, it should preferably involve or follow a detailed training needs analysis. Although the cost benefits of training are often difficult to quantify, a simulator is frequently easier to justify if plant familiarisation and training can be provided in advance of on-the-job experience. This is particularly true if the target operators have little hands-on experience of similar plant either in terms of processes or the operator interface. (author).

High-speed BWR power plant simulations on the special-purpose peripheral processor AD10

International Nuclear Information System (INIS)

Wulff, W.; Cheng, H.S.; Lekach, S.V.; Mallen, A.N.

1985-01-01

A newly developed technique is described for fast, on-line simulations of normal and accidental transients in nuclear power plants. The technique is based on the utilization of the special-purpose peripheral processor AD10, which is specifically designed for high-speed systems simulations through integration of large systems of nonlinear ordinary differential equations. The Peach Bottom-II Boiling Water Reactor power plant has been simulated and results are presented. It is shown that the new technique not only advances safety analyses but also supports plant monitoring, failure diagnosis and accident mitigation, as well as the training of nuclear power plant operators. (author)

Experience gained in the training of nuclear power plant operating personnel with nuclear power plant simulators

International Nuclear Information System (INIS)

Buettner, J.; Fueg, J.; Schlegel, G.

1980-01-01

The simulator of a PWR-type reactor with 1.200 MW was accomplished in September 1977. In January 1978, the simulator of a BWR-type reactor with 800 MW started operation. The American company Singer/Link supplied computer hardware and software; Kraftwerk Union AG supplied control room equipment, power plant data and acted as consulting engineers for the construction and acceptance of the simulators. This way it is ensured that the simulated process reflects the state of German nuclear engineering. (orig./DG) [de

Mathematical model for the simulation of PWR power plant

International Nuclear Information System (INIS)

Delfosse, C.

1979-01-01

A reactor simulator representing the principal characteristics of a nuclear power plant and their regulation has been developed. Special attention has been devoted to the simulation of the pressurizer, the steam turbine and the valves. Numerical tests have been realised in order to verify the speed of the calculations. (MDC)

Simulation of control performance under house load transients for nuclear power plant

International Nuclear Information System (INIS)

Liao Zhongyue; Wang Yuanlong; Tang Yuyuan; Liu Jiong

1999-01-01

The CATIA2 code is used to simulate the extreme normal transients--house load transients of Qinshan Phase II 600 MW nuclear power plant. The simulating results show that all of the reactor main parameters are operating in the allowable ranges, the reactor system is stable, and the control characteristics of the nuclear power plant is satisfactory. They are also good in agreement with Framatome's results

Application perspectives of simulation techniques CFD in nuclear power plants

International Nuclear Information System (INIS)

Galindo G, I. F.

2013-10-01

The scenarios simulation in nuclear power plants is usually carried out with system codes that are based on concentrated parameters networks. However situations exist in some components where the flow is predominantly 3-D, as they are the natural circulation, mixed and stratification phenomena. The simulation techniques of computational fluid dynamics (CFD) have the potential to simulate these flows numerically. The use of CFD simulations embraces many branches of the engineering and continues growing, however, in relation to its application with respect to the problems related with the safety in nuclear power plants, has a smaller development, although is accelerating quickly and is expected that in the future they play a more emphasized paper in the analyses. A main obstacle to be able to achieve a general acceptance of the CFD is that the simulations should have very complete validation studies, sometimes not available. In this article a general panorama of the state of the methods application CFD in nuclear power plants is presented and the problem associated to its routine application and acceptance, including the view point of the regulatory authorities. Application examples are revised in those that the CFD offers real benefits and are also presented two illustrative study cases of the application of CFD techniques. The case of a water recipient with a heat source in its interior, similar to spent fuel pool of a nuclear power plant is presented firstly; and later the case of the Boron dilution of a water volume that enters to a nuclear reactor is presented. We can conclude that the CFD technology represents a very important opportunity to improve the phenomena understanding with a strong component 3-D and to contribute in the uncertainty reduction. (Author)

The online simulation of core physics in nuclear power plant

International Nuclear Information System (INIS)

Zhao Qiang

2005-01-01

The three-dimensional power distribution in core is one of the most important status variables of nuclear reactor. In order to monitor the 3-D in core power distribution timely and accurately, the online simulation system of core physics was designed in the paper. This system combines core physics simulation with the data, which is from the plant and reactor instrumentation. The design of the system consists of the hardware part and the software part. The online simulation system consists of a main simulation computer and a simulation operation station. The online simulation system software includes of the real-time simulation support software, the system communication software, the simulation program and the simulation interface software. Two-group and three-dimensional neutron kinetics model with six groups delayed neutrons was used in the real-time simulation of nuclear reactor core physics. According to the characteristics of the nuclear reactor, the core was divided into many nodes. Resolving the neutron equation, the method of separate variables was used. The input data from the plant and reactor instrumentation system consist of core thermal power, loop temperatures and pressure, control rod positions, boron concentration, core exit thermocouple data, Excore detector signals, in core flux detectors signals. There are two purposes using the data, one is to ensure that the model is as close as the current actual reactor condition, and the other is to calibrate the calculated power distribution. In this paper, the scheme of the online simulation system was introduced. Under the real-time simulation support system, the simulation program is being compiled. Compared with the actual operational data, the elementary simulation results were reasonable and correct. (author)

An object-oriented simulation package for power plants

International Nuclear Information System (INIS)

Robinson, J.T.; Otaduy, P.J.

1987-01-01

This paper describes the application of object-oriented programming to the simulation of continuous/discrete processes such as nuclear power plants. Systems are modeled using this technique as a collection of objects that communicate by passing messages, which invoke methods that describe the state and dynamic behavior of objects. The objects themselves generally correspond to actual plant components, thus minimizing the representational mismatch between actual and modeled systems and facilitating their validation. Several concepts of object-oriented programming, in particular classes, inheritance, and message passing, have proved to be very useful for simulation. The use of these features are discussed and illustrated with examples

Using fire dynamics simulator to reconstruct a hydroelectric power plant fire accident.

Science.gov (United States)

Chi, Jen-Hao; Wu, Sheng-Hung; Shu, Chi-Min

2011-11-01

The location of the hydroelectric power plant poses a high risk to occupants seeking to escape in a fire accident. Calculating the heat release rate of transformer oil as 11.5 MW/m(2), the fire at the Taiwan Dajia-River hydroelectric power plant was reconstructed using the fire dynamics simulator (FDS). The variations at the escape route of the fire hazard factors temperature, radiant heat, carbon monoxide, and oxygen were collected during the simulation to verify the causes of the serious casualties resulting from the fire. The simulated safe escape time when taking temperature changes into account is about 236 sec, 155 sec for radiant heat changes, 260 sec for carbon monoxide changes, and 235-248 sec for oxygen changes. These escape times are far less than the actual escape time of 302 sec. The simulation thus demonstrated the urgent need to improve escape options for people escaping a hydroelectric power plant fire. © 2011 American Academy of Forensic Sciences.

Numerical simulation of a passive scalar transport from thermal power plants

Science.gov (United States)

Issakhov, Alibek; Baitureyeva, Aiymzhan

2017-06-01

The active development of the industry leads to an increase in the number of factories, plants, thermal power plants, nuclear power plants, thereby increasing the amount of emissions into the atmosphere. Harmful chemicals are deposited on the soil surface, remain in the atmosphere, which leads to a variety of environmental problems which are harmful for human health and the environment, flora and fauna. Considering the above problems, it is very important to control the emissions to keep them at an acceptable level for the environment. In order to do that it is necessary to investigate the spread of harmful emissions. The best way to assess it is the creating numerical simulation of gaseous substances' motion. In the present work the numerical simulation of the spreading of emissions from the thermal power plant chimney is considered. The model takes into account the physical properties of the emitted substances and allows to calculate the distribution of the mass fractions, depending on the wind velocity and composition of emissions. The numerical results were performed using the ANSYS Fluent software package. As a result, the results of numerical simulations and the graphs are given.

A full scope nuclear power plant simulator for multiple reactor types with virtual control panels

International Nuclear Information System (INIS)

Yonezawa, Hisanori; Ueda, Hiroki; Kato, Takahisa

2017-01-01

This paper summarizes a full scope nuclear power plant simulator for multiple reactor types with virtual control panels which Toshiba developed and delivered. After the Fukushima DAIICHI nuclear power plants accident, it is required that all the people who are engaged in the design, manufacturing, operation, maintenance, management and regulation for the nuclear power plant should learn the wide and deep knowledge about the nuclear power plant design including the severe accident. For this purpose, the training with a full scope simulator is one of the most suitable ways. However the existing full scope simulators which are consist of the control panels replica of the referenced plants are costly and they are hard to remodel to fit to the real plant of the latest condition. That's why Toshiba developed and delivered the new concept simulator system which covers multiple referenced plants even though they have different design like BWR and PWR. The control panels of the simulator are made by combining 69 large Liquid Crystal Display (LCD) panels with touch screen instead of a control panel replica of referenced plant. The screen size of the each panel is 42 inches and 3 displays are arranged in tandem for one unit and 23 units are connected together. Each panel displays switches, indicators, recorders and lamps with the Computer Graphics (CG) and trainees operate them with touch operations. The simulator includes a BWR and a PWR simulator model, which enable trainees to learn the wide and deep knowledge about the nuclear power plant of BWR and PWR reactor types. (author)

The German simulator center for the training of nuclear power plant operators

International Nuclear Information System (INIS)

Hoffmann, E.

1996-01-01

Simulator training for nuclear power plant operators in Germany is conducted in The Simulator Center in Essen. The companies operating The Center are KSG/GfS. KSG provides simulators, GfS performs the training. The German Simulator Center is equipped with five simulators in training, nine simulators are under construction and will be ready for training until the beginning of 1997. This institution serves 22 nuclear power plants units in Germany, Switzerland (NPP Goesgen-Daeniken) and the Netherlands (NPP Borssele) and trains 1,800 persons every year. As a common enterprise the company is owned by 12 utilities, which leads to the necessity to prepare common rules and guidelines for simulator specification, training of instructors, assessment of trainees, training material and preparation and methodical running of simulator courses

DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant

International Nuclear Information System (INIS)

Saphier, D.; Madell, J.; Dean, E.

1988-01-01

1 - Description of problem or function: DSNP (Dynamic Simulator for Nuclear Power-Plants) is a system of programs and data files by which a nuclear power plant, or part thereof, can be simulated. The acronym DSNP is used interchangeably for the DSNP language, the DSNP libraries, the DSNP pre-compiler, and the DSNP document generator. The DSNP language is a special-purpose, block-oriented digital- simulation language developed to facilitate the preparation of dynamic simulations of a large variety of nuclear power plants. It is a user-oriented language that permits the user to prepare simulation programs directly from power plant block diagrams and flow charts by recognizing the symbolic DSNP statements for the appropriate physical components and listing these statements in a logical sequence according to the flow of physical properties in the simulated power plant. Physical components of nuclear power plants are represented by functional blocks, or modules. Many of the more complex components are represented by several modules. The nuclear reactor, for example, has a kinetic module, a power distribution module, a feedback module, a thermodynamic module, a hydraulic module, and a radioactive heat decay module. These modules are stored in DSNP libraries in the form of a DSNP subroutine or function, a block of statements, a macro, or a combination of the above. Basic functional blocks such as integrators, pipes, function generators, connectors, and many auxiliary functions representing properties of materials used in nuclear power plants are also available. The DSNP pre-compiler analyzes the DSNP simulation program, performs the appropriate translations, inserts the requested modules from the library, links these modules together, searches necessary data files, and produces a simulation program in FORTRAN. FORTRAN is considered to be a subset of DSNP and can be inserted anywhere in the simulation program without restriction. I/O statements can be located anywhere in

Dynamic simulation of a direct carbonate fuel cell power plant

Energy Technology Data Exchange (ETDEWEB)

Ernest, J.B. [Fluor Daniel, Inc., Irvine, CA (United States); Ghezel-Ayagh, H.; Kush, A.K. [Fuel Cell Engineering, Danbury, CT (United States)

1996-12-31

Fuel Cell Engineering Corporation (FCE) is commercializing a 2.85 MW Direct carbonate Fuel Cell (DFC) power plant. The commercialization sequence has already progressed through construction and operation of the first commercial-scale DFC power plant on a U.S. electric utility, the 2 MW Santa Clara Demonstration Project (SCDP), and the completion of the early phases of a Commercial Plant design. A 400 kW fuel cell stack Test Facility is being built at Energy Research Corporation (ERC), FCE`s parent company, which will be capable of testing commercial-sized fuel cell stacks in an integrated plant configuration. Fluor Daniel, Inc. provided engineering, procurement, and construction services for SCDP and has jointly developed the Commercial Plant design with FCE, focusing on the balance-of-plant (BOP) equipment outside of the fuel cell modules. This paper provides a brief orientation to the dynamic simulation of a fuel cell power plant and the benefits offered.

Continuity and Innovation. 25 years of simulator training for nuclear power plants in Germany

International Nuclear Information System (INIS)

Lindauer, E.

2002-01-01

The first training simulator for nuclear power plant personnel in Germany was commissioned twenty-five years ago. This date was rather early, both when measured by the development of the German nuclear power program and when compared with the international situation. This farsighted decision demonstrates the importance nuclear power plant operators attach to the sound training of plant personnel. The consistent, and also costly, further development over the past twenty-five years shows that this attitude has not changed. A modern simulator center was built at a total cost of approx. 250 million Euro which can be characterized briefly as follows: - 13 full simulators cover most specific features of existing nuclear power plants. These simulators are backfitted continuously and represent the current state of simulation technology. - Their experience over many years has allowed the staff of approx. 140 to accumulate a high level of know-how in training and simulator operation. Learning from experience is greatly assisted by the fact that all activities are concentrated at one center. - The way in which the center is organized ensures close cooperation with the nuclear power plants responsible for the training of their personnel. - There is a systematic training concept which is being actively developed further. Some of the main developments in recent years include training for emergencies; intensified training in behavioral aspects, such as communication and leadership; the use of simulators for emergency drills; testing of modifications, etc. (orig.) [de

Fluid distribution network and steam generators and method for nuclear power plant training simulator

International Nuclear Information System (INIS)

Alliston, W.H.; Johnson, S.J.; Mutafelija, B.A.

1975-01-01

A description is given of a training simulator for the real-time dynamic operation of a nuclear power plant which utilizes apparatus that includes control consoles having manual and automatic devices corresponding to simulated plant components and indicating devices for monitoring physical values in the simulated plant. A digital computer configuration is connected to the control consoles to calculate the dynamic real-time simulated operation of the plant in accordance with the simulated plant components to provide output data including data for operating the control console indicating devices. In the method and system for simulating a fluid distribution network of the power plant, such as that which includes, for example, a main steam system which distributes steam from steam generators to high pressure turbine steam reheaters, steam dump valves, and feedwater heaters, the simultaneous solution of linearized non-linear algebraic equations is used to calculate all the flows throughout the simulated system. A plurality of parallel connected steam generators that supply steam to the system are simulated individually, and include the simulation of shrink-swell characteristics

Nuclear power plant simulation facility evaluation methodology

International Nuclear Information System (INIS)

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

1985-01-01

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

Introduction of Electrical System Simulation and Analysis Used in Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Sang Hak; Jeong, Woo Sung

2015-01-01

The purpose of this paper is to introduce the simulation methods and tools to analyse and predict the performance of the electric power distribution system for nuclear power plants (NPPs) in Korea. Electrical System design engineers are to evaluate the load flow, bus voltage profiles, short circuit levels, motor starting, and fast bus transfer under various plant operating conditions and to verify the adequacy of power distribution System for a reliable power supply to plant loads under various disturbances which could jeopardize a safe and reliable operation of nuclear power plants. (authors)

Nuclear power plant C and I design verification by simulation

International Nuclear Information System (INIS)

Storm, Joachim; Yu, Kim; Lee, D.Y

2003-01-01

An important part of the Advanced Boiling Water Reactor (ABWR) in the Taiwan NPP Lungmen Units no.1 and no.2 is the Full Scope Simulator (FSS). The simulator was to be built according to design data and therefore, apart from the training aspect, a major part of the development is to apply a simulation based test bed for the verification, validation and improvement of plant design in the control and instrumentation (C and I) areas of unit control room equipment, operator Man Machine Interface (MMI), process computer functions and plant procedures. Furthermore the Full Scope Simulator will be used after that to allow proper training of the plant operators two years before Unit no.1 fuel load. The article describes scope, methods and results of the advanced verification and validation process and highlights the advantages of test bed simulation for real power plant design and implementation. Subsequent application of advanced simulation software tools like instrumentation and control translators, graphical model builders, process models, graphical on-line test tools and screen based or projected soft panels, allowed a team to fulfil the task of C and I verification in time before the implementation of the Distributed Control and Information System (DCIS) started. An additional area of activity was the Human Factors Engineering (HFE) for the operator MMI. Due to the fact that the ABWR design incorporates a display-based operation with most of the plant components, a dedicated verification and validation process is required by NUREG-0711. In order to support this activity an engineering test system had been installed for all the necessary HFE investigations. All detected improvements had been properly documented and used to update the plant design documentation by a defined process. The Full Scope Simulator (FSS) with hard panels and stimulated digital control and information system are in the final acceptance test process with the end customer, Taiwan Power Company

Modelling of core protection and monitoring system for PWR nuclear power plant simulator

International Nuclear Information System (INIS)

Jung Kun Lee; Byoung Sung Han

1997-01-01

A nuclear power plant simulator was developed for Younggwang units 3 and 4 nuclear power plant (YGN Nos 3 and 4) in Korea; it has been in operation on training center since November 1996. The core protection calculator (CPC) and the core operating limit supervisory system (COLSS) for the simulator were also developed. The CPC is a digital computer-based core protection system, which performs on-line calculation of departure from nucleate boiling ratio (DNBR) and local power density (LPD). It initiates reactor trip when the core conditions exceed designated DNBR or LPD limitations. The COLSS is designed to assist operators by implementing the limiting conditions for operations in the technical specifications. With these systems, it is possible to increase capacity factor and safety of nuclear power plants, because the COLSS data can show accurate operation margin to plant operators and the CPC can protect reactor core. In this study, the function of CPC/COLSS is analyzed in detail, and then simulation model for CPC/COLSS is presented based on the function. Compared with the YGN Nos 3 and 4 plant operation data and CEDIPS/COLSS FORTRAN code test results, the predictions with the model show reasonable results. (Author)

Atucha II nuclear power plant digital simulation

International Nuclear Information System (INIS)

Santome, D.; Rovere, L.A.T.

1987-01-01

This paper describes the start-up of a digital simulation code apt to be performed in real time of Atucha II nuclear power plant, foreseeing its subsequent usage in a Basic Principles Simulator. Adaptability and modification of existing routines and development of modules in order to incorporate the necessary variables dynamics to couple the different modes, were the main tasks. The mathematical model used allows the representation of the following sub-systems: a) a reactor's core point model, which comprehends the neutronic kinetics, fission and decaying powers, thermal transfer and Xe-poisoning calculation; b) pressurizer, which considers two sub-systems that may or may not be in thermodynamic equilibrium, both in two phases; c) coolants and moderators bonds considering separate moderator loops with the aim of introducing asymmetric perturbations; d) secondary sub-subsystem, which includes the feed water loop, pumps, steam generators and control valves; e) steam generators; f) control and safety systems, including power control, steam generators levels, moderator's temperature primary loop system, limitations and protection. (Author)

Development of Northeast Asia Nuclear Power Plant Accident Simulator.

Science.gov (United States)

Kim, Juyub; Kim, Juyoul; Po, Li-Chi Cliff

2017-06-15

A conclusion from the lessons learned after the March 2011 Fukushima Daiichi accident was that Korea needs a tool to estimate consequences from a major accident that could occur at a nuclear power plant located in a neighboring country. This paper describes a suite of computer-based codes to be used by Korea's nuclear emergency response staff for training and potentially operational support in Korea's national emergency preparedness and response program. The systems of codes, Northeast Asia Nuclear Accident Simulator (NANAS), consist of three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. To quickly assess potential doses to the public in Korea, NANAS includes specific reactor data from the nuclear power plants in China, Japan and Taiwan. The completed simulator is demonstrated using data for a hypothetical release. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Power station simulators

International Nuclear Information System (INIS)

Zanobetti

1989-01-01

The number and the variety of simulators have gown to such an extent that it has become necessary to classify the numerous types now available. Simulators are of paramount importance for the design of nuclear power plants, for optimizing their efficiency and for the training of their operators: factors that contribute to their overall security. This book contains chapters on the following subjects: the development of power plant simulators, the components and classification of simulators, simulator technology, simulator performance and problems in simulator training

Utilization of a full-scope simulation for training the operating personel of nuclear power plants

International Nuclear Information System (INIS)

Mathias, S.G.

1987-01-01

A full-scope simulator of the Angra-2 Nuclear Power Plant has been installed at the NUCLEBRAS Training Center in Mambucaba - close to the site where that Plant is being built -, the goal of providing training for the operating personnel of the KWU-design nuclear power plants to be installed in Brazil. Due to the delays which occurred in the construction of Angra-2, NUCLEBRAS has established an extensive program for the utilization of the simulator for the training of operators for German nuclear power plants and for Spain's Trillo Plant. Besides yielding profits to NUCLEBRAS, that program is resulting in considerable experience in the area of nuclear power plant operators' training generating international recognition to the NUCLEBRAS Training Center. (Author) [pt

Solar power plant performance evaluation: simulation and experimental validation

Science.gov (United States)

Natsheh, E. M.; Albarbar, A.

2012-05-01

In this work the performance of solar power plant is evaluated based on a developed model comprise photovoltaic array, battery storage, controller and converters. The model is implemented using MATLAB/SIMULINK software package. Perturb and observe (P&O) algorithm is used for maximizing the generated power based on maximum power point tracker (MPPT) implementation. The outcome of the developed model are validated and supported by a case study carried out using operational 28.8kW grid-connected solar power plant located in central Manchester. Measurements were taken over 21 month's period; using hourly average irradiance and cell temperature. It was found that system degradation could be clearly monitored by determining the residual (the difference) between the output power predicted by the model and the actual measured power parameters. It was found that the residual exceeded the healthy threshold, 1.7kW, due to heavy snow in Manchester last winter. More important, the developed performance evaluation technique could be adopted to detect any other reasons that may degrade the performance of the P V panels such as shading and dirt. Repeatability and reliability of the developed system performance were validated during this period. Good agreement was achieved between the theoretical simulation and the real time measurement taken the online grid connected solar power plant.

Engineered safeguards systems and method in nuclear power plant training simulator

International Nuclear Information System (INIS)

Desalu, A.A.

1977-01-01

A method and system is disclosed for simulating the dynamic realtime operation of a nuclear power plant wherein a plurality of remote control devices provide input data to a digital computer to calculate physical values corresponding to plant operation to operate indicating devices for monitoring the physical operation of the plant. 24 claims, 29 figures

Computer models and simulations of IGCC power plants with Canadian coals

Energy Technology Data Exchange (ETDEWEB)

Zheng, L.; Furimsky, E.

1999-07-01

In this paper, three steady state computer models for simulation of IGCC power plants with Shell, Texaco and BGL (British Gas Lurgi) gasifiers will be presented. All models were based on a study by Bechtel for Nova Scotia Power Corporation. They were built by using Advanced System for Process Engineering (ASPEN) steady state simulation software together with Fortran programs developed in house. Each model was integrated from several sections which can be simulated independently, such as coal preparation, gasification, gas cooling, acid gas removing, sulfur recovery, gas turbine, heat recovery steam generation, and steam cycle. A general description of each process, model's overall structure, capability, testing results, and background reference will be given. The performance of some Canadian coals on these models will be discussed as well. The authors also built a computer model of IGCC power plant with Kellogg-Rust-Westinghouse gasifier, however, due to limitation of paper length, it is not presented here.

Use of control room simulators for training of nuclear power plant personnel

International Nuclear Information System (INIS)

2004-09-01

Safety analysis and operational experience consistently indicate that human error is the greatest contributor to the risk of a severe accident in a nuclear power plant. Subsequent to the Three Mile Island accident, major changes were made internationally in reducing the potential for human error through improved procedures, information presentation, and training of operators. The use of full scope simulators in the training of operators is an essential element of these efforts to reduce human error. The operators today spend a large fraction of their time training and retraining on the simulator. As indicated in the IAEA Safety Guide on Recruitment, Qualification and Training of Personnel for Nuclear Power Plants, NS-G-2.8, 2002, representative simulator facilities should be used for training of control room operators and shift supervisors. Simulator training should incorporate normal, abnormal and accident conditions. The ability of the simulator to closely represent the actual conditions and environment that would be experienced in a real situation is critical to the value of the training received. The objective of this report is to provide nuclear power plant (NPP) managers, training centre managers and personnel involved with control room simulator training with practical information they can use to improve the performance of their personnel. While the emphasis in this publication is on simulator training of control room personnel using full scope simulators, information is also provided on how organizations have effectively used control room simulators for training of other NPP personnel, including simulators other than full-scope simulators

The design, development and operation of a compact nuclear power plant simulator

International Nuclear Information System (INIS)

Lynch, M.F.

1987-01-01

This paper discusses the philosophy and technological considerations necessary for constructing and utilizing a plant specific compact nuclear power plant simulator, how it compares to full scope replica simulators, engineering simulators, part task simulators and basic principles training simulators. Included in this discussion are the design process, scope of simulation, the manufacturing process, test programs and experiences with operator training. Items addressed include the applicability and use of a compact simulator, how well it reproduces the actual reference plant, how well the transferral of knowledge is accomplished and what financial considerations need to be evaluated. This paper tries to provide the details on just how this type of machine was designed and developed by Westinghouse for the Swiss Utility, Nordostschweizerische Kraftwerke (NOK) AG

Accident sequences simulated at the Juragua nuclear power plant

International Nuclear Information System (INIS)

Carbajo, J.J.

1998-01-01

Different hypothetical accident sequences have been simulated at Unit 1 of the Juragua nuclear power plant in Cuba, a plant with two VVER-440 V213 units under construction. The computer code MELCOR was employed for these simulations. The sequences simulated are: (1) a design-basis accident (DBA) large loss of coolant accident (LOCA) with the emergency core coolant system (ECCS) on, (2) a station blackout (SBO), (3) a small LOCA (SLOCA) concurrent with SBO, (4) a large LOCA (LLOCA) concurrent with SBO, and (5) a LLOCA concurrent with SBO and with the containment breached at time zero. Timings of important events and source term releases have been calculated for the different sequences analyzed. Under certain weather conditions, the fission products released from the severe accident sequences may travel to southern Florida

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

Energy Technology Data Exchange (ETDEWEB)

Ronald L. Boring

2012-10-01

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

Solar power plant performance evaluation: simulation and experimental validation

International Nuclear Information System (INIS)

Natsheh, E M; Albarbar, A

2012-01-01

In this work the performance of solar power plant is evaluated based on a developed model comprise photovoltaic array, battery storage, controller and converters. The model is implemented using MATLAB/SIMULINK software package. Perturb and observe (P and O) algorithm is used for maximizing the generated power based on maximum power point tracker (MPPT) implementation. The outcome of the developed model are validated and supported by a case study carried out using operational 28.8kW grid-connected solar power plant located in central Manchester. Measurements were taken over 21 month's period; using hourly average irradiance and cell temperature. It was found that system degradation could be clearly monitored by determining the residual (the difference) between the output power predicted by the model and the actual measured power parameters. It was found that the residual exceeded the healthy threshold, 1.7kW, due to heavy snow in Manchester last winter. More important, the developed performance evaluation technique could be adopted to detect any other reasons that may degrade the performance of the P V panels such as shading and dirt. Repeatability and reliability of the developed system performance were validated during this period. Good agreement was achieved between the theoretical simulation and the real time measurement taken the online grid connected solar power plant.

STAR Power, an Interactive Educational Fusion CD with a Dynamic, Shaped Tokamak Power Plant Simulator

Science.gov (United States)

Leuer, J. A.; Lee, R. L.; Kellman, A. G.; Chapman Nutt, G. C., Jr.; Holley, G.; Larsen, T. A.

2000-10-01

We describe an interactive, educational fusion adventure game developed within our fusion education program. The theme of the adventure is start-up of a state-of-the-art fusion power plant. To gain access to the power plant control room, the student must complete several education modules, including topics on building an atom, fusion reactions, charged particle motion in electric and magnetic fields, and building a power plant. Review questions, a fusion video, library material and glossary provide additional resources. In the control room the student must start-up a complex, dynamic fusion power plant. The simulation model contains primary elements of a tokamak based device, including a magnetic shaper capable of producing limited and diverted elongated plasmas. A zero dimensional plasma model based on ITER scaling and containing rate based conservation equations provides dynamic feedback through major control parameters such as toroidal field, fueling rate and heating. The game is available for use on PC and Mac. computers. Copies will be available at the conference.

Sustained qualification process for full scope nuclear power plant simulators

International Nuclear Information System (INIS)

Pirson, J.; Stubbe, E.; Vanhoenacker, L.

1994-01-01

In the past decade, simulator training for all nuclear power plant operators has evolved into a vital requirement. To assure a correct training, the simulator qualification process is an important issue not only for the initial validation but also following major simulator updates, which are necessary during the lifetime of the simulator. In order to avoid degradation of the simulator validated software, the modifications have to be introduced according to a rigorous methodology and a practical requalification process has to be applied. Such methodology has to be enforced at every phase of the simulator construction or updating process from plant data package constitution, over simulator software development to simulator response qualification. The initial qualification and requalification process is based on the 3 levels identified by the ANSI/ANS 3-5 standard for steady-state, operational transients and accident conditions. For the initial certification of the full scope simulators in Belgium, a practical qualification methodology has been applied, which has been adapted into a set of non regression tests for the requalification after major simulator updates. (orig.) (4 refs., 3 figs.)

Angra 1 nuclear power plant full scope simulator development project

Energy Technology Data Exchange (ETDEWEB)

Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da, E-mail: edsel@eletronuclear.gov.br, E-mail: lccast@eletronuclear.gov.br, E-mail: nilogar@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (SCO/ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Superintendencia de Coordenacao da Operacao; Zazo, Francisco Javier Lopez; Ruiz, Jose Antonio, E-mail: jlopez@tecnatom.es, E-mail: jaruiz@tecnatom.es [Tecnatom S.A., San Sebastian de los Reyes, Madrid (Spain)

2015-07-01

Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

Angra 1 nuclear power plant full scope simulator development project

International Nuclear Information System (INIS)

Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da

2015-01-01

Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

NCS--a software for visual modeling and simulation of PWR nuclear power plant control system

International Nuclear Information System (INIS)

Cui Zhenhua

1998-12-01

The modeling and simulation of nuclear power plant control system has been investigated. Some mathematical models for rapid and accurate simulation are derived, including core models, pressurizer model, steam generator model, etc. Several numerical methods such as Runge-Kutta Method and Treanor Method are adopted to solve the above system models. In order to model the control system conveniently, a block diagram-oriented visual modeling platform is designed. And the Discrete Similarity Method is used to calculate the control system models. A corresponding simulating software, NCS, is developed for researching on the control systems of commercial nuclear power plant. And some satisfactory results are obtained. The research works will be of referential and applying value to design and analysis of nuclear power plant control system

Modeling and simulation of pressurized water reactor power plant

International Nuclear Information System (INIS)

Wang, S.J.

1983-01-01

Two kinds of balance of plant (BOP) models of a pressurized water reactor (PWR) system are developed in this work - the detailed BOP model and the simple BOP model. The detailed model is used to simulate the normal operational performance of a whole BOP system. The simple model is used to combine with the NSSS model for a whole plant simulation. The trends of the steady state values of the detailed model are correct and the dynamic responses are reasonable. The simple BOP model approach starts the modelling work from the overall point of view. The response of the normalized turbine power and the feedwater inlet temperature to the steam generator of the simple model are compared with those of the detailed model. Both the steady state values and the dynamic responses are close to those of the detailed model. The simple BOP model is found adequate to represent the main performance of the BOP system. The simple balance of plant model was coupled with a NSSS model for a whole plant simulation. The NSSS model consists of the reactor core model, the steam generator model, and the coolant temperature control system. A closed loop whole plant simulation for an electric load perturbation was performed. The results are plausible. The coupling effect between the NSSS system and the BOP system was analyzed. The feedback of the BOP system has little effect on the steam generator performance, while the performance of the BOP system is strongly affected by the steam flow rate from the NSSS

The design of VR-CATS for power plant simulator using virtual reality

International Nuclear Information System (INIS)

Park, S. Y.; Yoo, H. J.; Lee, M. S.; Hong, J. H.; Lee, Y. K.

2001-01-01

In Hadong fossil power plant simulator project (1998. 1 ∼ 2000. 7), KEPRI applied virtual reality to the simulator. To provide more efficient operator training, KEPRI further developed the virtual reality technology into VR-CATS( Virtual Reality Computer Assistance Training System), a web-based multimedia training system with virtual reality technologies, in KNPEC-2 projects. By visualizing nuclear power plant system with stereoscopic 3-graphics in this project, VR-CATS enable trainee to navigate whole nuclear power plants including high radiation areas and other restricted areas. In addition, instructors can train the local operators to operate the local valves and other equipment in the local area of the plant. It aims at helping trainees understand system locations and system functions more easily. And, by reproducing main control room with stereoscopic 3-D graphics and linking it with P and ID, operating procedures, and plant components, Virtual panels maximize training effects. During the classroom training, the instructor can acess the stand-by host computer of the simulator through a network. This enables the instructor to can operate the simulator with only soft-panel. With the soft-panel, the instructor can activate any malfunction that he wants to instruct, show the trends of major parameters to the trainee and discuss with them. This desktop simulator function helps trainee to understand basic symptoms of the accidents. With CBT, operators can easily understand why some parameters are increasing or decreasing and what they should to mak the system stable. The VR-CATS for Uljin equips with much stronger and higher level virtual environment. First, all components of the virtual plant are linked with P and ID, ISO drawings, and engineering database. In addition, virtual MCR provides much immersive environment with such virtual reality equipment as HMD and data glove. Operators can also do collaboration work in the network through avatar, real

Evaluation of a Kalman filter based power pressurizer instrument failure detection system implemented on a nuclear power plant training simulator

International Nuclear Information System (INIS)

Seegmiller, D.S.

1984-01-01

The usefulness of a nuclear power plant training simulator for developing and testing modern estimation and control applications for nuclear power plants is demonstrated. A Kalman filter based instrument failure detection technique for a pressurized water reactor pressurizer is implemented on the Department of Energy N Reactor Training Simulator. This real-time failure detection method computes the first two moments (mean and variance) of each element of a normalized filter innovations vector. Failed pressurizer instrumentation can be detected by comparing these moments to the known statistical properties of the steady state, linear Kalman fitler innovations sequence. The capabilities of the detection system are evaluated using simulated plant transients and instrument failures

Training of nuclear power plant personnel on Czechoslovak WWER-440 simulator

International Nuclear Information System (INIS)

Dugovic, M.

1985-01-01

The aim of simulator training is to train personnel for control work observing technical and technological regulations of nuclear power plant operation. Training is implemented in two forms: basic training and recurrent training. The daily regime of the training course is divided into theoretical education, simulator training and evaluation. Simulator training is oriented to the preparation of the workplace, presentation, controlled intermittent work and independent control work. (J.C.)

Modelling and use of the STUDS nuclear power plant simulator

International Nuclear Information System (INIS)

Blomberg, P.E.; Espefaelt, R.; Josefsson, R.; Schuch, N.

1979-02-01

The simulator models, belonging to the STUDS-family, which have been developed at Studsvik in cooperation with the Swedish utilities, are briefly described. The scope of the simulation is presented and the fundamental equations used are indicated. Different needs have led to a number of STUDS-versions for BWR and PWR type plants, primarily intended for application in the following fields: 1) transient analysis, 2) system design verification, 3) control system development, 4) testing of new on-line techniques for disturbance analysis, noise analysis, man-machine communication, etc, 5) training of power plant operators, 6) operational planning. The simulator was initially implemented on a hybrid computer system but more recent work has led to pure digital simulations maintaining the real time feature and adding features like snapshot and backtrack. The latest version for PWR is used at the Halden Project and in the general purpose COMPACT SIMULATOR: developed at Studsvik and made commercially available. (author)

Design and use of an engineering simulator for power plant and training simulator updates

International Nuclear Information System (INIS)

Sharawy, P.S.; Kennard, J.R.; Chou, Q.B.

1990-01-01

The advancement in real-time simulators has been facilitated by the availability of increasingly powerful computing devices at reduced costs for use in conjunction with high-fidelity simulation software. Ontario Hydro's commitment to the safe and reliable operation of its nuclear power plants was one of the factors which influenced its decision to build a plant-replica operator training simulator for each of its nuclear generating stations. This investment soon proved to have advantages beyond those originally envisaged. It become apparent that because the software developed for these simulators met rigorous acceptance criteria, it could be used on an engineering simulator to effectively investigate problems occurring at the stations. It could also serve as a design aid for station modifications. Encouraged by the success of early experimentation in the use of its training simulators for concept validation and verification, Ontario Hydro is developing a low-cost central facility - the Instrumentation and Control Engineering Simulator (ICES) - for use in its design work. This facility incorporates the software of its training simulators and includes a user-friendly generic interface which enables designers to configure and operate it. Inclusion of the engineering simulator in all phases of the design process, from the original concept to implementation and verification, will make it possible to shorten the design period significantly while achieving a high level of quality. It will also facilitate the rapid retrofit of simulators to reflect station modifications. This paper will recount Ontario Hydro's experience in the use of simulators for design work and will specifically discuss the design features and system performance of its engineering simulator

Development of module-based simulation system for nuclear power plant

International Nuclear Information System (INIS)

Yoshikawa, H.

1990-01-01

Module-based Simulation System (MSS) has been developed to realize a new software environment enabling versatile dynamic simulation of a complex nuclear power plant system flexibly. Described in the paper are (i) fundamental methods utilized in MMS and its software systemization, (ii) development of human interface system to help users in generating integrated simulation programs automatically, and (iii) development of an intelligent user support system for helping users in the two phases of automatical semantic diagnosis and consultation to automatic input data setup for the MSS-generated programs

Real-time modelling of a ventilation system for a power plant simulator

International Nuclear Information System (INIS)

Kocher, P.; Welfonder, E.

1992-01-01

This paper describes how to simulate in real-time the ventilation system of a nuclear power plant. The simulation is made under difficult computing time conditions. The ventilation system program is part of a simulator which simulates the whole nuclear power plant process in realtime. Therefore the ventilation system is split up into several smaller units. For each of these process units a real-time module has been developed, being as simple as possible but nevertheless coming close enough to the real dynamic behaviour. After that the simple real-time modules are linked together to form the total dynamic model ''ventilation system''. The continuous dynamic model developed is numerically integrated by the Euler method. The stability of this explicit method is maintained by special modelling measures such as the increasing of too low flow resistances or the limitation of too high gain factors. At the end of the paper some curves, recorded at the simulator, illustrate the behaviour of the ventilation system in the case of an accident. (author)

Microcomputer simulation of PWR power plant pressurizer

International Nuclear Information System (INIS)

Araujo, L.R.A. de; Calixto Neto, J.; Martinez, A.S.; Schirru, R.

1990-01-01

It is presented a method for the simulation of the pressurizer behavior of a PWR power plant. The method was implanted in a microcomputer, and it considers all the devices for the pressure control (spray and relief valves, heaters, controller, etc.). The physical phenomena and the PID (Proportional + Integral + Derivative) controller were mathematically represented by linear relations, uncoupled, discretized in the time. There are three different algorithms which take into account the non-linear effects introduced by the variation of the physical properties due to the temperature and pressure, and also the mutual effects between the physical phenomena and the PID controller. (author)

4D Simulation for Nuclear Power Plant Construction

International Nuclear Information System (INIS)

Jeong, Seo G.; Suh, Kune Y.

2006-01-01

For the timely and competitive response to rapidly changing energy environment at the turn of millennium, there is a desperate need to build the nuclear power plant (NPP) in the virtual reality of digital engineering prior to commissioning. To construct a NPP is a highly integrated, voluminous project. Verification of design and initial planning is prerequisite to construction to confirm optimal fabrication and high productivity. This paper presents the design feasibility by simulating the initial construction plan of NPP using four-dimensional (4D) simulation. The virtual reality method, using three dimensional (3D) computer-aided design (CAD) model, enables various designs in the project launching stage to be promptly and exactly previewed

A digital simulation of a pressurizer in a PWR nuclear power plant

International Nuclear Information System (INIS)

Sato, E.F.

1980-11-01

A model for pressurizer digital simulation of a PWR nuclear power plant during transients, considering all pressurizer control features, is presented. The pressurizer is divided into two regions separated by a water-vapor interface and non-equilibrium conditions are considered. The particular thermodynamic process followed during insurge and outsurges is determined at each instant of analysis without any previous assumption. The pressure behavior is defined by an explicit equation in any of four possible pressurizer thermodynamic conditions. Thermodynamic properties of steam and water are computed by ASME subroutines and the mathematical formulation presented in this study was programed in FORTRAN IV for a Burroughs-6700 digital computer system. This program was employed to simulate the Shippingport Atomic Power Station and Almirante Alvaro Alberto Nuclear Power Plant - Unit 1 pressurizers. The test results compared with experimental or vendor data show the validity of this analysis method. (Author) [pt

Development of AC-DC power system simulator

International Nuclear Information System (INIS)

Ichikawa, Tatsumi; Ueda, Kiyotaka; Inoue, Toshio

1984-01-01

A modeling and realization technique is described for realtime plant dynamics simulation of nuclear power generating unit in AC-DC power system simulator. Dynamic behavior of reactor system and steam system is important for investigation a further adequate unit control and protection system to system faults in AC and DC power system. Each unit of two nuclear power generating unit in the power system simulator consists of micro generator, DC motors, flywheels and process computer. The DC motor and flywheel simulates dynamic characteristics of steam turbine, and process computer simulates plant dynamics by digital simulation. We have realized real-time plant dynamics simulation by utilizing a high speed process I/O and a high speed digital differential analyzing processor (DDA) in which we builted a newly developed simple plant model. (author)

Markov approach to evaluate the availability simulation model for power generation system in a thermal power plant ,

Directory of Open Access Journals (Sweden)

Avdhesh Kr. Sharma

2012-10-01

Full Text Available In recent years, the availability of power plants has become increasingly important issue in most developed and developing countries. This paper aims to propose a methodology based on Markov approach to evaluate the availability simulation model for power generation system (Turbine in a thermal power plant under realistic working environment. The effects of occurrence of failure/course of actions and availability of repair facilities on system performance have been investigated. Higher availability of the components/equipments is inherently associated with their higher reliability and maintainability. The power generation system consists of five subsystems with four possible states: full working, reduced capacity, reduced efficiency and failed state. So, its availability should be carefully evaluated in order to foresee the performance of the power plant. The availability simulation model (Av. has been developed with the help of mathematical formulation based on Markov Birth-Death process using probabilistic approach. For this purpose, first differential equations have been generated. These equations are then solved using normalizing condition so as to determine the steady state availability of power generation system. In fact, availability analysis is very much effective in finding critical subsystems and deciding their preventive maintenance program for improving availability of the power plant as well as the power supply. From the graphs illustrated, the optimum values of failure/repair rates for maximum availability, of each subsystem is analyzed and then maintenance priorities are decided for all subsystems.The present paper highlights that in this system, Turbine governing subsystem is most sensitive demands more improvement in maintainability as compared to the other subsystems. While Turbine lubrication subsystem is least sensitive.

Application of virtual reality to simulation in nuclear power plant

International Nuclear Information System (INIS)

Liu Pengfei; Yang Yanhua; Yang Yongmu; Duan Dongdong; Luo Jie

2008-01-01

Based on detailed analysis of the structure and key techniques of a virtual reality system, the applications of virtual reality to simulation in nuclear power plant (NPP) were developed. In order to meet the requirement of simulation in NPP, motion simulation of control rod drive system, walking system inside the containment and virtual main control room were presented. A simulator of NPP was connected to interchange dynamic data between virtual main control room and the simulator. The simulating results show that the technique of virtual reality can be applied well to the simulation inside containment, which is filled with activity material, and the simulation of virtual main control room, where human factors must be considered. It also can be used well to design virtual education and training system of NPP. (authors)

Application of process simulation for evaluation of ecologically benefical developments in thermal power plant technology

International Nuclear Information System (INIS)

Schuster, G.

2000-04-01

Responsibility for the environment and a sustainable utilization of resources gain also in the production of electric power more and more importance. For this reason existing power generation processes have to be improved and alternatives to existing processes have to be developed. As a first step in this procedure process simulation is a powerful tool to evaluate the potentials of new developments. In this work it is shown, how new thermal power processes are modeled and simulated based on well-known thermodynamic and chemical correlations. Processes for thermal power plants using lignite with high water content and biomass as fuel are studied. In each case simulations are carried out for complete plants including all important unit operations. Based on a conventional thermal power plant for lignite different variants for efficiency improvement by fuel drying are examined. Additionally the potential of a process with gasification and gas turbine is discussed. Compared to a lignite power plant the preconditions for a biomass power plant are different. A promising option for the future seems to be small, decentralized combined heat and power plants. Therefore a process with simple and compact design including gasifier and gas turbine is regarded and sensitivity analyses are carried out. As well as for the lignite processes possible improvements by fuel drying are studied. The basis lignite power plant (drying in an impact rotor mill with hot flue gas) has an overall electric efficiency of 36 %. Alternative fuel drying processes (reducing water content from 54 w % to 10 w %) can increase efficiency to nearly 43 %. Using integrated air-blown gasification combined with gas turbine and steam turbine and additional fuel drying raises the efficiency up to 49 % in the case of cold gas cleanup and up to 50 percent in the case of hot gas cleanup. Efficiencies of the regarded biomass power plants are in the range of about 20 % (with a biomass water content of 25 w %). By

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Gilberto Espinosa-Paredes

2012-01-01

Full Text Available The loss-of-coolant accident (LOCA simulation in the boiling water reactor (BWR of Laguna Verde Nuclear Power Plant (LVNPP at 105% of rated power is analyzed in this work. The LVNPP model was developed using RELAP/SCDAPSIM code. The lack of cooling water after the LOCA gets to the LVNPP to melting of the core that exceeds the design basis of the nuclear power plant (NPP sufficiently to cause failure of structures, materials, and systems that are needed to ensure proper cooling of the reactor core by normal means. Faced with a severe accident, the first response is to maintain the reactor core cooling by any means available, but in order to carry out such an attempt is necessary to understand fully the progression of core damage, since such action has effects that may be decisive in accident progression. The simulation considers a LOCA in the recirculation loop of the reactor with and without cooling water injection. During the progression of core damage, we analyze the cooling water injection at different times and the results show that there are significant differences in the level of core damage and hydrogen production, among other variables analyzed such as maximum surface temperature, fission products released, and debris bed height.

Performance and Simulation of a Stand-alone Parabolic Trough Solar Thermal Power Plant

Science.gov (United States)

Mohammad, S. T.; Al-Kayiem, H. H.; Assadi, M. K.; Gilani, S. I. U. H.; Khlief, A. K.

2018-05-01

In this paper, a Simulink® Thermolib Model has been established for simulation performance evaluation of Stand-alone Parabolic Trough Solar Thermal Power Plant in Universiti Teknologi PETRONAS, Malaysia. This paper proposes a design of 1.2 kW parabolic trough power plant. The model is capable to predict temperatures at any system outlet in the plant, as well as the power output produced. The conditions that are taken into account as input to the model are: local solar radiation and ambient temperatures, which have been measured during the year. Other parameters that have been input to the model are the collector’s sizes, location in terms of latitude and altitude. Lastly, the results are presented in graphical manner to describe the analysed variations of various outputs of the solar fields obtained, and help to predict the performance of the plant. The developed model allows an initial evaluation of the viability and technical feasibility of any similar solar thermal power plant.

Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

Energy Technology Data Exchange (ETDEWEB)

Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

2013-03-01

The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

Numerical simulation of flow field in shellside of heat exchanger in nuclear power plant

International Nuclear Information System (INIS)

Wang Xinliang; Qiu Jinrong; Gong Zili

2010-01-01

Heat exchanger is the important equipment of nuclear power plant. Numerical simulation can give the detail information inside the heat exchange, and has been an effective research method. The geometric structure of shell-and-tube heat exchanger is very complex and it is difficult to simulate the whole flow field presently. According to the structure characteristics of the heat exchanger, a periodic whole-section calculation model was presented. The numerical simulation of flow field in shellside of heat exchange of a nuclear power plant was done by using this model. The results of simulation show that heat transfer in the periodic section of the heat exchange is uniform, the heat transfer is enhanced by using baffles in heat exchange, and frictional resistance is primary from the effect of segmental baffles. (authors)

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

International Nuclear Information System (INIS)

Srivastava, Gaurava Deep; Kulkarni, R.D.

2015-01-01

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

A powerful tool for plant specific simulations

International Nuclear Information System (INIS)

Boucau, J.; Ofstun, R.

1988-01-01

Following the Three Mile Island (TMI) accident, special emphasis has been placed by the Utilities and Safety Authorities on the training of plant operators and engineers to make them more familiar with the dynamic behavior of the plant in post-accident conditions. With a view to providing transient response under realistic operating conditions, concerns were raised over: the use of conservative safety analysis models for analyzing operational and accident transients; the ability to dynamically simulate the expected operator actions, and the need to simulate the plant during long term cooling recovery. To meet these requirements, an interactive, user friendly, cost efficient dynamic model capable of simulating two-phase conditions is needed. In response to these post-TMI concerns, Westinghouse has developed, the Transient Real-Time Engineering Analysis Tool (TREAT) which is a general purpose interactive thermal-hydraulic network code for thermal-hydraulic transient analysis. The applications of TREAT are numerous and range from engineering studies to plant operator training using the newly developed TREAT SIMULATOR. The purpose of this paper is to describe the TREAT program and potential applications. Special emphasis will be drawn at a plant specific training application performed for a French 4-loop plant

Simulation of Valve Operation for Flow Interrupt Test in Nuclear Power Plant

International Nuclear Information System (INIS)

Kim, Jae Hyung; Shin, Dae Yong; Shin, Dong Woo; Kim, Charn Jung; Lee, Jung Hee

2012-01-01

The valve used in nuclear power plant must be qualified for the function according to the KEPIC MF. The test valve must be selected by shape and size, which is given by KEPIC MF. In the functional test, the mathematical model for the valve operation is needed. The mathematical model must be verified by the test, whose method and procedure is defined in KEPIC MF. The lack of analytical technique has lead to the poor mathematical model, with which the functional test for the big valve is impossible with analytical method. Especially, the tank and rupture disk in the flow test is not considered and the result of the analysis is so different to the real one. In these days, the 3D model for the flow interrupt test makes more accurate analysis. And no facility about functional test reduces the research will for the nuclear power plant valve. For this problem, the test facility for the functional test of the valve and pump in nuclear power plant has been made until 2012. With the test facility, the research project related the valve were initiated in KIMM( Korea Institute of Machinery and Materials). And the joint project to SNU(Seoul National University) has been going on the numerical analysis for the valve in nuclear power plant. Using the commercial software and user subroutine, UDF, the co-simulation with multi-body dynamic and fluid flow analysis and the addition of tank and rupture disk to the user subroutine make possible to simulate the flow interrupt test numerically. This is not simple and regular analysis, which was introduced in user subroutine. In order to simulate the real situation, the engineering work, related mathematical model, and the programming in the user subroutine are needed. This study is on the making the mathematical model for the functional test of the valve in nuclear power plan. The functional test is the real test procedure and defined in KEPIC MF

The added value of the replica simulators in the exploitation of nuclear power plants

International Nuclear Information System (INIS)

Diaz Giron, P. a.; Ortega, F.; Rivero, N.

2011-01-01

Nuclear power plants full scope replica simulators were in the past solely designed following operational personnel training criteria. Nevertheless, these simulators not only feature a high replica control room but also provide an accurate process response. Control room replica simulators are presently based on complex technological platforms permitting highest physical and functional fidelity, allowing to be used as versatile and value added tools in diverse plants operation and maintenance activities. In recent years. Tecnatom has extended the use of such simulators to different engineering applications. this article intends to identify the simulators use in training and other applications beyond training. (Author)

Catalytic Activity and Deactivation of SO2 Oxidation Catalysts in Simulated Power Plant Flue Gases

DEFF Research Database (Denmark)

Masters, Stephen G.; Chrissanthopoulos, Asthanassios; Eriksen, Kim Michael

1997-01-01

The catalyst deactivation and the simultaneious formation of compounds in commercial SO2 oxidation catalysts have been studied by combined activity measurements and in situ EPR spectroscopy in the temperature range 350-480 C in wet and dry simulated power plant flue gas.......The catalyst deactivation and the simultaneious formation of compounds in commercial SO2 oxidation catalysts have been studied by combined activity measurements and in situ EPR spectroscopy in the temperature range 350-480 C in wet and dry simulated power plant flue gas....

Modeling and numerical techniques for high-speed digital simulation of nuclear power plants

International Nuclear Information System (INIS)

Wulff, W.; Cheng, H.S.; Mallen, A.N.

1987-01-01

Conventional computing methods are contrasted with newly developed high-speed and low-cost computing techniques for simulating normal and accidental transients in nuclear power plants. Six principles are formulated for cost-effective high-fidelity simulation with emphasis on modeling of transient two-phase flow coolant dynamics in nuclear reactors. Available computing architectures are characterized. It is shown that the combination of the newly developed modeling and computing principles with the use of existing special-purpose peripheral processors is capable of achieving low-cost and high-speed simulation with high-fidelity and outstanding user convenience, suitable for detailed reactor plant response analyses

Comparison of piping models for digital power plant simulators

International Nuclear Information System (INIS)

Sowers, G.W.

1979-08-01

Two piping models intended for use in a digital power plant simulator are compared. One is a finite difference approximation to the partial differential equation called PIPE, and the other is a function subroutine that acts as a delay operator called PDELAY. The two models are compared with respect to accuracy and execution time. In addition, the stability of the PIPE model is determined. The PDELAY model is found to execute faster than the PIPE model with comparable accuracy

Atucha I nuclear power plant transients analysis

International Nuclear Information System (INIS)

Castano, J.; Schivo, M.

1987-01-01

A program for the transients simulation thermohydraulic calculation without loss of coolant (KWU-ENACE development) to evaluate Atucha I nuclear power plant behaviour is used. The program includes systems simulation and nuclear power plants control bonds with real parameters. The calculation results show a good agreement with the output 'protocol' of various transients of the nuclear power plant, keeping the error, in general, lesser than ± 10% from the variation of the nuclear power plant's state variables. (Author)

Simulation of the dynamic behaviour of the secondary circuit of a WWER-440 type nuclear power plant Pt. 1

International Nuclear Information System (INIS)

Gacs, A.; Janosy, J.S.; Kiss, Zs.

1987-07-01

This report describes the simulation model of the secondary circuit of a WWER-440 type nuclear power plant. The goal of this modelling is to simulate normal and small abnormal transients in a Basic Principles Simulator. The earlier reports describing the dynamic simulation of primary circuit of a WWER-440 nuclear power plant are KFKI--1983-127 and KFKI--1985-08. At present the controllers of the secondary circuit are not simulated. Finally, some simulation results are presented. (author)

Meeting summary of the second CSNI specialist meeting on simulators and plant analyzers - Current Issues in Nuclear Power Plant Simulation

International Nuclear Information System (INIS)

1998-01-01

The Second CSNI Specialist Meeting on Simulators and Plant Analyzers: Current Issues in Nuclear Power Plant Simulation was held in Espoo, Finland, from September 29 through October 2, 1997. It was organised by CSNI Principal Working Group on Coolant System Behaviour (PWG2), Task Group on Thermal Hydraulic Applications (TG-THA), in co-operation with Technical Research Centre of Finland. The meeting in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. The previous meeting held in Lappeenranta, Finland, in 1992 collected some 85 participants from 12 countries, presenting a total of 40 papers. The meeting was structured into 6 sessions covering the important aspects of development and use of simulators and plant analyzers: Session I: New objectives, Requirements and Concepts. This session covered the progress experienced since the 1. simulator meeting and tried to address the changing role of simulators based on the changes in users' needs and developing possibilities. Session II: Trends in Simulation Technology. This session was reserved for studying the current trends in the simulation technology: software environments, visualisation, simulator configuration tools, programming languages and computer systems. Session III: Training and human factor studies using simulators. This session was created for studying the status of different uses of simulators such as educational simulators, human factor studies and integrated safety assessment in addition to traditional training. Regarding to the severe accidents, a question was raised whether the simulator use should be for training or education. Session IV: Modelling techniques. The session on modelling techniques was included to cover recent developments in the modelling techniques applicable to training

Part-task simulator of a WWER-440 type nuclear power plant unit

International Nuclear Information System (INIS)

Palecek, P.

1990-01-01

In the present paper the design of a part-task simulator for WWER-440 type nuclear power plant units by the CEZ (Czech Power Works) Concern is reported. This part-task simulator has been designed for the training of NPP operating personnel. It includes a central computer that is coupled with the training work places and the trainer place. Interchange of information is performed by functional keyboards and semigraphical colour displays. The process is simulated, also in real time scale, on the basis of dynamic models. In addition to the precision of the models used, great importance has primarily been attached to plasticity of information presentation. The part-task simulator may be applied to simulation and demonstration as well as to teaching purposes. The paper presents the achieved state of implementation of the part-task simulator and points out some further stage of evolution. (author)

Numerical simulation methods of fires in nuclear power plants

International Nuclear Information System (INIS)

Keski-Rahkonen, O.; Bjoerkman, J.; Heikkilae, L.

1992-01-01

Fire is a significant hazard to the safety of nuclear power plants (NPP). Fire may be serious accident as such, but even small fire at a critical point in a NPP may cause an accident much more serious than fire itself. According to risk assessments a fire may be an initial cause or a contributing factor in a large part of reactor accidents. At the Fire Technology and the the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) fire safety research for NPPs has been carried out in a large extent since 1985. During years 1988-92 a project Advanced Numerical Modelling in Nuclear Power Plants (PALOME) was carried out. In the project the level of numerical modelling for fire research in Finland was improved by acquiring, preparing for use and developing numerical fire simulation programs. Large scale test data of the German experimental program (PHDR Sicherheitsprogramm in Kernforschungscentral Karlsruhe) has been as reference. The large scale tests were simulated by numerical codes and results were compared to calculations carried out by others. Scientific interaction with outstanding foreign laboratories and scientists has been an important part of the project. This report describes the work of PALOME-project carried out at the Fire Technology Laboratory only. A report on the work at the Nuclear Engineering Laboratory will be published separatively. (au)

Development of the simulation system IMPACT for analysis of nuclear power plant severe accidents

International Nuclear Information System (INIS)

Naitoh, Masanori; Ujita, Hiroshi; Nagumo, Hiroichi

1997-01-01

The Nuclear Power Engineering Corporation (NUPEC) has initiated a long-term program to develop the simulation system IMPACT for analysis of hypothetical severe accidents in nuclear power plants. IMPACT employs advanced methods of physical modeling and numerical computation, and can simulate a wide spectrum of senarios ranging from normal operation to hypothetical, beyond-design-basis-accident events. Designed as a large-scale system of interconnected, hierarchical modules, IMPACT's distinguishing features include mechanistic models based on first principles and high speed simulation on parallel processing computers. The present plan is a ten-year program starting from 1993, consisting of the initial one-year of preparatory work followed by three technical phases: Phase-1 for development of a prototype system; Phase-2 for completion of the simulation system, incorporating new achievements from basic studies; and Phase-3 for refinement through extensive verification and validation against test results and available real plant data

Solution and implementation of project ''Simulator of WWER-440 nuclear power plant''

International Nuclear Information System (INIS)

Koukal, V.

1985-01-01

The time data are given of the development and construction of the simulator of a WWER-440 nuclear power plant unit. The individual tasks are summed up which are related to the project implementation, and cooperating institutions and enterprises are listed. (J.C.)

Dynamic simulation of combined cycle power plant cycling in the electricity market

International Nuclear Information System (INIS)

Benato, A.; Bracco, S.; Stoppato, A.; Mirandola, A.

2016-01-01

Highlights: • The flexibility of traditional power plants have become of primary importance. • Three dynamic models of the same single pressure HRSG are built. • The plant dynamic behaviour is predicted. • A lifetime calculation procedure is proposed and tested. • The drum lifetime reduction is estimated. - Abstract: The energy markets deregulation coupled with the rapid spread of unpredictable energy sources power units are stressing the necessity of improving traditional power plants flexibility. Cyclic operation guarantees high profits in the short term but, in the medium-long time, cause a lifetime reduction due to thermo-mechanical fatigue, creep and corrosion. In this context, Combined Cycle Power Plants are the most concerned in flexible operation problems. For this reason, two research groups from two Italian universities have developed a procedure to estimate the devices lifetime reduction with a particular focus on steam drums and superheaters/reheaters. To assess the lifetime reduction, it is essential to predict the thermodynamic variables trend in order to describe the plant behaviour. Therefore, the core of the procedure is the power plant dynamic model. At this purpose, in this paper, three different dynamic models of the same single pressure Combined Cycle Gas Turbine are presented. The models have been built using three different approaches and are used to simulate plant behaviour under real operating conditions. Despite these differences, the thermodynamic parameters time profiles are in good accordance as presented in the paper. At last, an evaluation of the drum lifetime reduction is performed.

System Simulation of Nuclear Power Plant by Coupling RELAP5 and Matlab/Simulink

International Nuclear Information System (INIS)

Meng Lin; Dong Hou; Zhihong Xu; Yanhua Yang; Ronghua Zhang

2006-01-01

Since RELAP5 code has general and advanced features in thermal-hydraulic computation, it has been widely used in transient and accident safety analysis, experiment planning analysis, and system simulation, etc. So we wish to design, analyze, verify a new Instrumentation And Control (I and C) system of Nuclear Power Plant (NPP) based on the best-estimated code, and even develop our engineering simulator. But because of limited function of simulating control and protection system in RELAP5, it is necessary to expand the function for high efficient, accurate, flexible design and simulation of I and C system. Matlab/Simulink, a scientific computation software, just can compensate the limitation, which is a powerful tool in research and simulation of plant process control. The software is selected as I and C part to be coupled with RELAP5 code to realize system simulation of NPPs. There are two key techniques to be solved. One is the dynamic data exchange, by which Matlab/Simulink receives plant parameters and returns control results. Database is used to communicate the two codes. Accordingly, Dynamic Link Library (DLL) is applied to link database in RELAP5, while DLL and S-Function is applied in Matlab/Simulink. The other problem is synchronization between the two codes for ensuring consistency in global simulation time. Because Matlab/Simulink always computes faster than RELAP5, the simulation time is sent by RELAP5 and received by Matlab/Simulink. A time control subroutine is added into the simulation procedure of Matlab/Simulink to control its simulation advancement. Through these ways, Matlab/Simulink is dynamically coupled with RELAP5. Thus, in Matlab/Simulink, we can freely design control and protection logic of NPPs and test it with best-estimated plant model feedback. A test will be shown to illuminate that results of coupling calculation are nearly the same with one of single RELAP5 with control logic. In practice, a real Pressurized Water Reactor (PWR) is

Control of power plants and power systems. Proceedings

International Nuclear Information System (INIS)

Canales-Ruiz, R.

1996-01-01

The 88 papers in this volume constitute the proceedings of the International Federation of Automatic Control Symposium held in Mexico in 1995. The broad areas which they cover are: self tuning control; power plant operations; dynamic stability; fuzzy logic applications; power plants modelling; artificial intelligence applications; power plants simulation; voltage control; control of hydro electric units; state estimation; fault diagnosis and monitoring systems; system expansion and operation planning; security assessment; economic dispatch and optimal load flow; adaptive control; distribution; transient stability and preventive control; modelling and control of nuclear plant; knowledge data bases for automatic learning methods applied to power system dynamic security assessment; control of combined cycle units; power control centres. Separate abstracts have been prepared for the three papers relating to nuclear power plants. (UK)

Authorization of nuclear power plant control room personnel: Methods and practices with emphasis on the use of simulators

International Nuclear Information System (INIS)

2006-07-01

In 2002 the IAEA published a revision to Safety Guide NS-G-2.8, Recruitment, Qualification and Training of Personnel for Nuclear Power Plants. This Safety Guide provides recommendations on the authorization of designated personnel who have a direct impact on nuclear safety. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional report be prepared that provided information on the practices in Member States on the use of simulators in the authorization of control room staff. This publication has been prepared in response to that recommendation. In gathering information for the report, Member States were asked to: respond to a survey on the use of simulators and the involvement of regulatory body in operator authorization; and to complete a questionnaire on their practices in authorizing control room staff. Safety analysis and operating experience consistently indicate that human error is a major contributor to nuclear power plant (NPP) accident risk. With the recent world wide emphasis and implementation of full scope simulators for nuclear power plant personnel training, operators spend a large portion of their training time on simulators. As described in the foreword to IAEA-TECDOC-1411, Use of Control Room Simulators for Training of Nuclear Power Plant Personnel, simulators provide operators an opportunity to learn and practice the abilities that are required in accident and infrequently used plant evolutions. Because of their fidelity, full scope simulators are now used by most Member States in the authorization examinations of control room personnel. This situation is becoming more common as more plants acquire modern full scope plant referenced simulators. This publication provides information and examples based upon experience in a variety of Member States. The body of the report provides general information that represents the practices of the Member States that contributed to the

Simulation research on multivariable fuzzy model predictive control of nuclear power plant

International Nuclear Information System (INIS)

Su Jie

2012-01-01

To improve the dynamic control capabilities of the nuclear power plant, the algorithm of the multivariable nonlinear predictive control based on the fuzzy model was applied in the main parameters control of the nuclear power plant, including control structure and the design of controller in the base of expounding the math model of the turbine and the once-through steam generator. The simulation results show that the respond of the change of the gas turbine speed and the steam pressure under the algorithm of multivariable fuzzy model predictive control is faster than that under the PID control algorithm, and the output value of the gas turbine speed and the steam pressure under the PID control algorithm is 3%-5% more than that under the algorithm of multi-variable fuzzy model predictive control. So it shows that the algorithm of multi-variable fuzzy model predictive control can control the output of the main parameters of the nuclear power plant well and get better control effect. (author)

Dynamic simulation of a circulating fluidized bed boiler system part II: Simulation of a boiler system operating in a power plant

International Nuclear Information System (INIS)

Kim, Seong Il; Choi, Sang Min; Yang, Jong In

2016-01-01

A case of dynamic performance simulation model of a CFB boiler is presented in this study. The dynamic system of a CFB boiler in an operating power plant and the transient behavior of sub-models is described in the accompanying paper, Part I. The current paper, Part II, describes the model extension for the CFB boiler system in a power plant. The open loop model in Paper I was expanded by applying a set of PID (Proportional-integral-differential) control loops. In the control loop, pressure, temperature, mass flow rate of the main steam, the drum water level and the oxygen level at the stack were controlled. Dynamic performance was simulated to check the response of the closed control loop. Finally, performance of the total boiler system for a range of operation load of the power plant was simulated, where the parameters were calculated and control variables were maintained at the set values by PID control. Dynamic performance of a boiler at a selected load variation case was simulated and compared with actual measurements and their transient response characteristics were discussed. The simulation can also directly produce useful operation parameters, which are not measurable, but could be used for engineering evaluation

Dynamic simulation of a circulating fluidized bed boiler system part II: Simulation of a boiler system operating in a power plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Seong Il; Choi, Sang Min; Yang, Jong In [Dept. of Mechanical Engineering, Korea Advanced Institute of Science and Technology, Daejeon(Korea, Republic of)

2016-12-15

A case of dynamic performance simulation model of a CFB boiler is presented in this study. The dynamic system of a CFB boiler in an operating power plant and the transient behavior of sub-models is described in the accompanying paper, Part I. The current paper, Part II, describes the model extension for the CFB boiler system in a power plant. The open loop model in Paper I was expanded by applying a set of PID (Proportional-integral-differential) control loops. In the control loop, pressure, temperature, mass flow rate of the main steam, the drum water level and the oxygen level at the stack were controlled. Dynamic performance was simulated to check the response of the closed control loop. Finally, performance of the total boiler system for a range of operation load of the power plant was simulated, where the parameters were calculated and control variables were maintained at the set values by PID control. Dynamic performance of a boiler at a selected load variation case was simulated and compared with actual measurements and their transient response characteristics were discussed. The simulation can also directly produce useful operation parameters, which are not measurable, but could be used for engineering evaluation.

Development of nuclear power plant monitoring system with neutral network using on-line PWR plant simulator

International Nuclear Information System (INIS)

Nabeshima Kunihiko; Suzuki Katsuo; Nose, Shoichi; Kudo, Kazuhiko

1996-01-01

The purpose of this paper is to demonstrate a nuclear power plant monitoring system using artificial neural network (ANN). The major advantages of the monitoring system are that a multi-output process system can be modelled using measurement information without establishing any mathematical expressions. The dynamics model of reactor plant was constructed by using three layered auto-associative neural network with backpropagation learning algorithm. The basic idea of anomaly detection method is to monitor the deviation between process signals measured from actual plant and corresponding output signals from the ANN plant model. The simulator used is a self contained system designed for training. Four kinds of simulated malfunction caused by equipment failure during steady state operation were used to evaluate the capability of the neural network monitoring system. The results showed that this monitoring system detected the symptom of small anomaly earlier than the prevailing alarm system. (author). 7 refs, 7 figs, 2 tabs

Development of nuclear power plant monitoring system with neutral network using on-line PWR plant simulator

Energy Technology Data Exchange (ETDEWEB)

Kunihiko, Nabeshima; Katsuo, Suzuki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan); Nose, Shoichi; Kudo, Kazuhiko [Kyushu Univ., Fukuoka (Japan). Faculty of Engineering

1997-12-31

The purpose of this paper is to demonstrate a nuclear power plant monitoring system using artificial neural network (ANN). The major advantages of the monitoring system are that a multi-output process system can be modelled using measurement information without establishing any mathematical expressions. The dynamics model of reactor plant was constructed by using three layered auto-associative neural network with backpropagation learning algorithm. The basic idea of anomaly detection method is to monitor the deviation between process signals measured from actual plant and corresponding output signals from the ANN plant model. The simulator used is a self contained system designed for training. Four kinds of simulated malfunction caused by equipment failure during steady state operation were used to evaluate the capability of the neural network monitoring system. The results showed that this monitoring system detected the symptom of small anomaly earlier than the prevailing alarm system. (author). 7 refs, 7 figs, 2 tabs.

Numerical Simulation of Groundwater Flow at Kori Nuclear Power Plant Site

International Nuclear Information System (INIS)

Sohn, Wook; Sohn, Soon Whan; Chon, Chul Min; Kim, Kue Youn

2010-01-01

Recently, the understanding of hydrogeological characteristics of nuclear power sites is getting more importance with increasing public concerns over the environment since such understanding is essential for an environmentally friendly operation of plants. For such understanding, the prediction of groundwater flow pattern onsite plays the most critical role since it is the most dynamic of the factors to be considered. In this study, the groundwater flow at the Kori Plant 1 site has been simulated numerically with aim of providing fundamental information needed for improving the understanding of the hydrogeological characteristics of the site

Simulation analysis of earthquake response of nuclear power plant to the 2003 Miyagi-Oki earthquake

International Nuclear Information System (INIS)

Yoshihiro Ogata; Kiyoshi Hirotani; Masayuki Higuchi; Shingo Nakayama

2005-01-01

On May 26, 2003 an earthquake of magnitude scale 7.1 (Japan Meteorological Agency) occurred just offshore of Miyagi Prefecture. This was the largest earthquake ever experienced by the nuclear power plant of Tohoku Electric Power Co. in Onagawa (hereafter the Onagawa Nuclear Power Plant) during the 19 years since it had started operations in 1984. In this report, we review the vibration characteristics of the reactor building of the Onagawa Nuclear Power Plant Unit 1 based on acceleration records observed at the building, and give an account of a simulation analysis of the earthquake response carried out to ascertain the appropriateness of design procedure and a seismic safety of the building. (authors)

Simulation of temperature distribution, BOD, and DO by thermal effluents of power plants

International Nuclear Information System (INIS)

Haeuser, J.

1977-01-01

A transient one, two, or three dimensional numerical model for simulation of heat load by power plants is presented. Water quality is determined by three parameters: temperature, biological oxygen demand (BOD), and disolved oxygen (DO). (orig.) [de

Development of nuclear power plant simulators for Soviet-designed nuclear reactors

International Nuclear Information System (INIS)

Kohut, P.; Tutu, N.K.; Cleary, E.J.; Erickson, K.G.; Yoder, J.; Kroshilin, A.

2001-01-01

The US Department of Energy (US DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators, are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper

PEGASO - simulation model for the operation of nuclear power plants for planning purposes

International Nuclear Information System (INIS)

Ribeiro, A.A.T.; Muniz, A.A.

1979-07-01

The utilization manual for PEGASO is presented, consisting of a set of programs whose objective is to simulate the monthly operation of nuclear power plants (up to 10 NPP), determining the principal physical parameters and criticality. (Author) [pt

Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

2005-04-01

Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

Simulation of a coal-fired power plant using mathematical programming algorithms in order to optimize its efficiency

International Nuclear Information System (INIS)

Tzolakis, G.; Papanikolaou, P.; Kolokotronis, D.; Samaras, N.; Tourlidakis, A.; Tomboulides, A.

2012-01-01

Since most of the world's electric energy production is mainly based on fossil fuels and need for better efficiency of the energy conversion systems is imminent, mathematical programming algorithms were applied for the simulation and optimization of a detailed model of an existing lignite-fired power plant in Kozani, Greece (KARDIA IV). The optimization of its overall thermal efficiency, using as control variables the mass flow rates of the steam turbine extractions and the fuel consumption, was performed with the use of the simulation and optimization software gPROMS. The power plant components' mathematical models were imported in software by the authors and the results showed that further increase to the overall thermal efficiency of the plant can be achieved (a 0.55% absolute increase) through reduction of the HP turbine's and increase of the LP turbine's extractions mass flow rates and the parallel reduction of the fuel consumption by 2.05% which also results to an equivalent reduction of the greenhouse gasses. The setup of the mathematical model and the flexibility of gPROMS, make this software applicable to various power plants. - Highlights: ► Modeling and simulation of the flue gases circuit of a specific plant. ► Designing of modules in gPROMS FO (Foreign Objects). ► Simulation of the complete detailed plant with gPROMS. ► Optimization using a non-linear optimization algorithm of the plant's efficiency.

Numerical simulation of the integrated solar/North Benghazi combined power plant

International Nuclear Information System (INIS)

Aldali, Y.; Morad, K.

2016-01-01

Highlights: • The thermodynamic and economic evaluation of power plant have been studied. • Saving and boosting modes are considered as the same solar field area. • Two modes of operation have been used and simulated on Libyan climate conditions. • The benefit/cost ratios are 1.74 and 1.30 for fuel saving and power boosting mode. • Fuel saving mode is more economical than power boosting mode. - Abstract: The aim of this paper is to study the thermodynamic performance of a proposed integrated solar/North Benghazi combined power plant under Libyan climatic conditions. The parabolic trough collector field with direct steam generation was considered as solar system. Two modes of operations with the same solar field area are considered: fuel saving mode in which the generated solar steam was used to preheat the combustion air in the gas turbine unit and power boosting mode in which the generated solar steam was added into the steam turbine for boosting the electrical power generated from steam turbine unit. Moreover, the economic impact of solar energy is assessed in the form of benefit/cost ratio to justify the substitution potential of such clean energy. This study shows that, for fuel saving mode: the annual saving of natural gas consumption and CO_2 emission are approximately 3001.56 and 7972.25 tons, respectively, in comparison with the conventional North Benghazi combined cycle power plant. For power boosting mode: the annual solar share of electrical energy is approximately 93.33 GW h. The economic analysis of solar supported plant has indicated that the benefit/cost ratios are 1.74 and 1.30 for fuel saving and power boosting mode, therefore, then fuel saving mode is more economical than power boosting mode for the same solar field area, moreover, it reduces the greenhouse CO_2 emission in order to avoid a collapse of the word climate.

Governor stability simulations of Svartisen power plant verified by the installed monitoring system on site

International Nuclear Information System (INIS)

Nielsen, T K; Kjeldsen, M

2010-01-01

Many Norwegian hydro power plants have complex lay-out with several reservoirs, broke intakes, surge shafts and even air cushion chambers. There are kilometers of excavated tunnels as well as long tail water systems. The stations are often equipped by multiple of turbines, both in series and parallel. A number of operation modes are therefore possible. Doing transient simulations and simulations of governor stability in the design phase, the problem is to find the worst case scenario regarding these operating modes. Svartisen power plant has been of particular interest these days. The power plant is originally designed for two 350 MW Francis turbines, however, only one turbine was installed. When designed, governor stability was regarded as problematic due to the long penstock. A long penstock will give a too high time constant for the hydraulic inertia. The main problem here is, however, the water hammer frequency that interferes with the governor performance. The frequency is in the same range as the cross frequency. Therefore the governor will react on these water hammer waves, which in its nature is notoriously unstable. The common solution is to build an air cushion and thereby increase the water hammer frequency above the cross frequency. The expenses were, however, deemed too high, and it was necessary to seek for other solutions. A pressure feedback on the governor was introduced in order to have stable operation at least for two turbines. With only one turbine installed, the pressure feedback has not been activated because, based on the simulations, it was regarded unnecessary. Even if the original simulations shows good stability margins when only one turbine is running, there has been some indications that the aggregate has suffered from instability. In 2004 Svartisen Power Plant was equipped with a comprehensive monitoring system. Both the turbine and the generator performance have been observed. This gives valuable information on how the hydropower

Governor stability simulations of Svartisen power plant verified by the installed monitoring system on site

Science.gov (United States)

Nielsen, T. K.; Kjeldsen, M.

2010-08-01

Many Norwegian hydro power plants have complex lay-out with several reservoirs, broke intakes, surge shafts and even air cushion chambers. There are kilometers of excavated tunnels as well as long tail water systems. The stations are often equipped by multiple of turbines, both in series and parallel. A number of operation modes are therefore possible. Doing transient simulations and simulations of governor stability in the design phase, the problem is to find the worst case scenario regarding these operating modes. Svartisen power plant has been of particular interest these days. The power plant is originally designed for two 350 MW Francis turbines, however, only one turbine was installed. When designed, governor stability was regarded as problematic due to the long penstock. A long penstock will give a too high time constant for the hydraulic inertia. The main problem here is, however, the water hammer frequency that interferes with the governor performance. The frequency is in the same range as the cross frequency. Therefore the governor will react on these water hammer waves, which in its nature is notoriously unstable. The common solution is to build an air cushion and thereby increase the water hammer frequency above the cross frequency. The expenses were, however, deemed too high, and it was necessary to seek for other solutions. A pressure feedback on the governor was introduced in order to have stable operation at least for two turbines. With only one turbine installed, the pressure feedback has not been activated because, based on the simulations, it was regarded unnecessary. Even if the original simulations shows good stability margins when only one turbine is running, there has been some indications that the aggregate has suffered from instability. In 2004 Svartisen Power Plant was equipped with a comprehensive monitoring system. Both the turbine and the generator performance have been observed. This gives valuable information on how the hydropower

Training simulator for nuclear power plant reactor control model and method

International Nuclear Information System (INIS)

Czerbuejewski, F.R.

1975-01-01

A description is given of a method and system for the real-time dynamic simulation of a nuclear power plant for training purposes, wherein a control console has a plurality of manual and automatic remote control devices for operating simulated control rods and has indicating devices for monitoring the physical operation of a simulated reactor. Digital computer means are connected to the control console to calculate data values for operating the monitoring devices in accordance with the control devices. The simulation of the reactor control rod mechanism is disclosed whereby the digital computer means operates the rod position monitoring devices in a real-time that is a fraction of the computer time steps and simulates the quick response of a control rod remote control lever together with the delayed response upon a change of direction

Process simulation of co-firing torrefied biomass in a 220 MWe coal-fired power plant

International Nuclear Information System (INIS)

Li, Jun; Zhang, Xiaolei; Pawlak-Kruczek, Halina; Yang, Weihong; Kruczek, Pawel; Blasiak, Wlodzimierz

2014-01-01

Highlights: • The performances of torrefaction based co-firing power plant are simulated by using Aspen Plus. • Mass loss properties and released gaseous components have been studied during biomass torrefaction processes. • Mole fractions of CO 2 and CO account for 69–91% and 4–27% in total torrefied gases. • The electrical efficiency reduced when increasing either torrefaction temperature or substitution ratio of biomass. - Abstract: Torrefaction based co-firing in a pulverized coal boiler has been proposed for large percentage of biomass co-firing. A 220 MWe pulverized coal-power plant is simulated using Aspen Plus for full understanding the impacts of an additional torrefaction unit on the efficiency of the whole power plant, the studied process includes biomass drying, biomass torrefaction, mill systems, biomass/coal devolatilization and combustion, heat exchanges and power generation. Palm kernel shells (PKS) were torrefied at same residence time but 4 different temperatures, to prepare 4 torrefied biomasses with different degrees of torrefaction. During biomass torrefaction processes, the mass loss properties and released gaseous components have been studied. In addition, process simulations at varying torrefaction degrees and biomass co-firing ratios have been carried out to understand the properties of CO 2 emission and electricity efficiency in the studied torrefaction based co-firing power plant. According to the experimental results, the mole fractions of CO 2 and CO account for 69–91% and 4–27% in torrefied gases. The predicted results also showed that the electrical efficiency reduced when increasing either torrefaction temperature or substitution ratio of biomass. A deep torrefaction may not be recommended, because the power saved from biomass grinding is less than the heat consumed by the extra torrefaction process, depending on the heat sources

Research on real-time simulation test for upgrades of digital I and C system in nuclear power plant

International Nuclear Information System (INIS)

Shi Ji; Jiang Mingyu; Ma Yunqin

2005-01-01

The developing trend that digital instrument and control (I and C) system will supplant traditional analog I and C system in nuclear power plant is emphasized. This paper introduces mathematical model of steam generator of full scope simulator for nuclear power plant. The independent real-time simulation system, which forms the interactive closed loop together with the steam generator control system, can be applied to provide a simulation target for upgrades of instrument and control system and the research of control schemes. At the same time, a simulation method for this purpose is presented in this paper. In this method all of the hardware and software are composed of real distributed control system except the model of controlled object. This will not only create favorable conditions for commissioning on site in the future, but also give a theoretical analysis for upgrades of digital I and C system in nuclear power plant. (authors)

Design Analysis of Power Extracting Unit of an Onshore OWC Based Wave Energy Power Plant using Numerical Simulation

Directory of Open Access Journals (Sweden)

Zahid Suleman

2011-07-01

Full Text Available This research paper describes design and analysis of power extracting unit of an onshore OWC (Oscillating Water Column based wave energy power plant of capacity about 100 kilowatts. The OWC is modeled as solid piston of a reciprocating pump. The power extracting unit is designed analytically by using the theory of reciprocating pumps and principles of fluid mechanics. Pro-E and ANSYS workbench softwares are used to verify the analytical design. The analytical results of the flow velocity in the turbine duct are compared with the simulation results. The results are found to be in good agreement with each other. The results achieved by this research would finally assist in the overall design of the power plant which is the ultimate goal of this research work.

A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION

International Nuclear Information System (INIS)

Mike Bockelie; Dave Swensen; Martin Denison

2002-01-01

This is the fifth Quarterly Technical Report for DOE Cooperative Agreement No: DE-FC26-00NT41047. The goal of the project is to develop and demonstrate a computational workbench for simulating the performance of Vision 21 Power Plant Systems. Within the last quarter, our efforts have become focused on developing an improved workbench for simulating a gasifier based Vision 21 energyplex. To provide for interoperability of models developed under Vision 21 and other DOE programs, discussions have been held with DOE and other organizations developing plant simulator tools to review the possibility of establishing a common software interface or protocol to use when developing component models. A component model that employs the CCA protocol has successfully been interfaced to our CCA enabled workbench. To investigate the software protocol issue, DOE has selected a gasifier based Vision 21 energyplex configuration for use in testing and evaluating the impacts of different software interface methods. A Memo of Understanding with the Cooperative Research Centre for Coal in Sustainable Development (CCSD) in Australia has been completed that will enable collaborative research efforts on gasification issues. Preliminary results have been obtained for a CFD model of a pilot scale, entrained flow gasifier. A paper was presented at the Vision 21 Program Review Meeting at NETL (Morgantown) that summarized our accomplishments for Year One and plans for Year Two and Year Three

Design of a solar updraft tower power plant for pakistan and its simulation in transys

International Nuclear Information System (INIS)

Khan, T.; Chaudhry, I.A.; Rehman, A.

2014-01-01

Solar updraft tower is a distinct and novel combination of three old concepts that are green house effect, chimney effect and wind turbine. It can be employed, with almost negligible maintenance cost, in electricity generation. Given the different climatic and economical conditions for different places, every region demands a specific design. As solar chimney power plant is a relatively new technology, much effort has not been done in evaluating the performances of the various plants. In this context, a solar updraft tower has been designed for the conditions of Pakistan (Lahore) and is simulated in TRNSYS to analyze the plant performance through different seasons and time of the year. The study reveals important results about the factors involved in determining the final output power produced. It is observed that the solar irradiance plays a more significant role in power generation than ambient temperature. The more the capacity of a plant to produce power, the more economical it would be. TRNSYS based program is presumed to be a handy mode of examining solar chimney power plants. (author)

A modular real time Operator Advisor expert system for installation on a full function nuclear power plant simulator

International Nuclear Information System (INIS)

Hajek, B.K.; Miller, D.W.; Bhatnagar, R.; Maresh, J.L.

1989-01-01

A knowledge-based expert system that uses the Generic Task approach is being developed to serve as an operator Advisor in the control room of a commercial nuclear power plant. Having identified the broad scope tasks performed by an operator in responding to abnormal plant conditions, our research team has modularized the Operator Advisor according to the tasks of (1) monitoring plant parameters, (2) classifying or diagnosing the abnormality, and (3) planning for execution of the procedures for recovery. The operator Advisor uses the Perry Nuclear Power Plant full-scope simulator as the reference system, and is currently being prepared for direct connection to the simulator

Behavioral simulation of a nuclear power plant operator crew for human-machine system design

International Nuclear Information System (INIS)

Furuta, K.; Shimada, T.; Kondo, S.

1999-01-01

This article proposes an architecture of behavioral simulation of an operator crew in a nuclear power plant including group processes and interactions between the operators and their working environment. An operator model was constructed based on the conceptual human information processor and then substantiated as a knowledge-based system with multiple sets of knowledge base and blackboard, each of which represents an individual operator. From a trade-off between reality and practicality, we adopted an architecture of simulation that consists of the operator, plant and environment models in order to consider operator-environment interactions. The simulation system developed on this framework and called OCCS was tested using a scenario of BWR plant operation. The case study showed that operator-environment interactions have significant effects on operator crew performance and that they should be considered properly for simulating behavior of human-machine systems. The proposed architecture contributed to more realistic simulation in comparison with an experimental result, and a good prospect has been obtained that computer simulation of an operator crew is feasible and useful for human-machine system design. (orig.)

Linguistic control of a nuclear power plant

International Nuclear Information System (INIS)

Feeley, J.J.; Johnson, J.C.

1987-01-01

A multivariable linguistic controller based on fuzzy set theory is discussed and its application to a pressurized water nuclear power plant control is illustrated by computer simulation. The nonlinear power plant simulation model has nine states, two control inputs, one disturbance input, and two outputs. Although relatively simple, the model captures the essential coupled nonlinear plant dynamics and is convenient to use for control system studies. The use of an adaptive version of the controller is also demonstrated by computer simulation

Optimal control systems in hydro power plants

International Nuclear Information System (INIS)

Babunski, Darko L.

2012-01-01

The aim of the research done in this work is focused on obtaining the optimal models of hydro turbine including auxiliary equipment, analysis of governors for hydro power plants and analysis and design of optimal control laws that can be easily applicable in real hydro power plants. The methodology of the research and realization of the set goals consist of the following steps: scope of the models of hydro turbine, and their modification using experimental data; verification of analyzed models and comparison of advantages and disadvantages of analyzed models, with proposal of turbine model for design of control low; analysis of proportional-integral-derivative control with fixed parameters and gain scheduling and nonlinear control; analysis of dynamic characteristics of turbine model including control and comparison of parameters of simulated system with experimental data; design of optimal control of hydro power plant considering proposed cost function and verification of optimal control law with load rejection measured data. The hydro power plant models, including model of power grid are simulated in case of island ing and restoration after breakup and load rejection with consideration of real loading and unloading of hydro power plant. Finally, simulations provide optimal values of control parameters, stability boundaries and results easily applicable to real hydro power plants. (author)

PUMA code simulation of recovery power transients after a short shutdown of the Embalse nuclear power plant

International Nuclear Information System (INIS)

Villar, Javier; Pomerantz, Marcelo E.

2003-01-01

A simulation of recovery power transients after a short shutdown on Embalse nuclear power plant equilibrium core with slightly enriched uranium fuel was performed in order to know the response of the reactor under such conditions. Also, comparison against the same event in a natural uranium core were done. No significant restrictions were found in operating with enriched fuel in the conditions of the analyzed event and in fact, slightly differences arose with natural uranium fuels. (author)

Predictors of operator performance at a simulated nuclear power plant control task

International Nuclear Information System (INIS)

Spettell, C.M.

1986-01-01

Male undergraduates participated in two experiments as operators of a simple dynamic nuclear power plant simulated on a personal computer. Their task involved monitoring the temperature and power output of the plant and controlling the flow of coolants and the position of the control rods to ensure that the plant operated at the desired temperature and output levels. Quality of performance was defined as the operator's ability to minimize the deviations in temperature and output from optimal values during the trials. Operator inputs and the status of all plant variables were recorded on-line every two seconds. Based on a review of human factors engineering and psychological literature, a number of personality, background, and process variables were measured and correlated with operator performance. Results of both experiments indicated that the strongest predictors of operator performance were the rate, magnitude, and accuracy of operator inputs. Input rate and magnitude were negatively related to overall performance; input accuracy was positively related to performance. These process variables and overall performance were relatively stable across trials of varying difficulty

Advanced modeling and simulation of integrated gasification combined cycle power plants with CO2-capture

International Nuclear Information System (INIS)

Rieger, Mathias

2014-01-01

The objective of this thesis is to provide an extensive description of the correlations in some of the most crucial sub-processes for hard coal fired IGCC with carbon capture (CC-IGCC). For this purpose, process simulation models are developed for four industrial gasification processes, the CO-shift cycle, the acid gas removal unit, the sulfur recovery process, the gas turbine, the water-/steam cycle and the air separation unit (ASU). Process simulations clarify the influence of certain boundary conditions on plant operation, performance and economics. Based on that, a comparative benchmark of CC-IGCC concepts is conducted. Furthermore, the influence of integration between the gas turbine and the ASU is analyzed in detail. The generated findings are used to develop an advanced plant configuration with improved economics. Nevertheless, IGCC power plants with carbon capture are not found to be an economically efficient power generation technology at present day boundary conditions.

Nuclear Power Plant Simulators: Goals and Evolution

International Nuclear Information System (INIS)

Miettinen, J.

2008-01-01

OECD / CSNI organised two Specialists Meetings in the field of plant simulators. With the development of the digital computation technology the progress in this field has been fast and there was a distinct need for reviewing the current state-of-the-art and the future development. The meeting were hosted by the Technical Research Centre of Finland (VTT), and they were arranged in 1992 and 1997. The paper discusses the evolution of the simulator technology and especially modelling of the main systems in the simulators used for the operator training and evaluation of the plant characteristics. The model development in 1990 was rapid due the increased computer capability and an interest towards the severe transients and full 3 D core neutronic simulation. The analysis models without real time calculation capability included a detailed model for the primary circuit, core or containment. The simulator models tried to describe the entire plant, but the primary circuit, core and containment were described with a robust, fast running model. After rapid development in the computational speed the detailed analysis models and robust simulator models do not need to be considered separately anymore. But there are new features, which force the simulator technology following the development. The hard control panels are replaced by CRT's, and / or the programmable digital technology replaces the analogue automation. The future full-scope simulators are replica's of the Crt control room and programmed automation. Only the process itself is calculated by the codes. One could ask, how with the fast development the state-of-the-art in 1992 and 1997 is useful still in 2008 in this fast developing area. One argument may be that understanding the history may help in creating the new understanding. And in fact many visions for the future were seen in those meeting. Some of them have been realized, some other not.

Steel corrosion products solubility under conditions simulating various water chemistry parameters in power plants

International Nuclear Information System (INIS)

Slobodov, A.A.; Kritskij, V.G.; Zarembo, V.I.; Puchkov, L.V.

1988-01-01

To simulate construction material corrosion product mass transfer model in power plant circuits calculation of iron oxide and hydroxide solubility, depending on water chemistry parameters: temperature, pH-value, content of dissolved in water hydrogen and oxygen, is carried out

Physical and financial virtual power plants

International Nuclear Information System (INIS)

Willems, Bert

2005-01-01

Regulators in Belgium and the Netherlands use different mechanisms to mitigate generation market power. In Belgium, antitrust authorities oblige the incumbent to sell financial Virtual Power Plants, while in the Netherlands regulators have been discussing the use of physical Virtual Power Plants. This paper uses a numerical game theoretic model to simulate the behavior of the generation firms and to compare the effects of both systems on the market power of the generators. It shows that financial Virtual Power Plants are better for society. (Author)

A code for simulation of human failure events in nuclear power plants: SIMPROC

International Nuclear Information System (INIS)

Gil, Jesus; Fernandez, Ivan; Murcia, Santiago; Gomez, Javier; Marrao, Hugo; Queral, Cesar; Exposito, Antonio; Rodriguez, Gabriel; Ibanez, Luisa; Hortal, Javier; Izquierdo, Jose M.; Sanchez, Miguel; Melendez, Enrique

2011-01-01

Over the past years, many Nuclear Power Plant organizations have performed Probabilistic Safety Assessments to identify and understand key plant vulnerabilities. As part of enhancing the PSA quality, the Human Reliability Analysis is essential to make a realistic evaluation of safety and about the potential facility's weaknesses. Moreover, it has to be noted that HRA continues to be a large source of uncertainty in the PSAs. Within their current joint collaborative activities, Indizen, Universidad Politecnica de Madrid and Consejo de Seguridad Nuclear have developed the so-called SIMulator of PROCedures (SIMPROC), a tool aiming at simulate events related with human actions and able to interact with a plant simulation model. The tool helps the analyst to quantify the importance of human actions in the final plant state. Among others, the main goal of SIMPROC is to check the Emergency Operating Procedures being used by operating crew in order to lead the plant to a safe shutdown plant state. Currently SIMPROC is coupled with the SCAIS software package, but the tool is flexible enough to be linked to other plant simulation codes. SIMPROC-SCAIS applications are shown in the present article to illustrate the tool performance. The applications were developed in the framework of the Nuclear Energy Agency project on Safety Margin Assessment and Applications (SM2A). First an introductory example was performed to obtain the damage domain boundary of a selected sequence from a SBLOCA. Secondly, the damage domain area of a selected sequence from a loss of Component Cooling Water with a subsequent seal LOCA was calculated. SIMPROC simulates the corresponding human actions in both cases. The results achieved shown how the system can be adapted to a wide range of purposes such as Dynamic Event Tree delineation, Emergency Operating Procedures and damage domain search.

Towards intelligent automation of power plant design and operations: The role of interactive simulations and distributed expert systems

International Nuclear Information System (INIS)

Otaduy, P.J.

1992-01-01

The design process of a power plant can be viewed as machine- chromosome engineering: When the final layout is implemented, the lifetime operating characteristics, constraints, strengths, and weaknesses of the resulting power-plant-specimen are durably determined. Hence, the safety, operability, maneuverability, availability, maintenance requirements, and costs of a power plant are directly related to the goodness of its electromechanical-genes. This paper addresses the desirability of incorporating distributed computing, distributed object management, and multimedia technologies to power plant engineering, in particular, to design and operations. The promise these technologies have for enhancing the quality and amount of engineering knowledge available, concurrently, online, to plant designers, maintenance crews, and operators is put into perspective. The role that advanced interactive simulations and expert systems will play in the intelligent automation of power plant design and operations is discussed

Upgrading of PWR plant simulators

International Nuclear Information System (INIS)

Wada, Tomonori; Sasaki, Kazunori; Nakaishi, Hirokazu.

1989-01-01

For the education and training of operators in electric power plants, simulators have been employed, and it is well known that their effect is great. There are operation training simulators which simulate the dynamic characteristics of plants and all the machinery and equipment that operators handle, and train the procedure of restoration at the time of abnormality in plants, education simulators which can analyze the dynamic characteristics of plants efficiently in a short time, and offer information by visualizing phenomena with three-dimensional display and others so as to be easily understandable, and forecast simulators which do the analysis forecasting plant behavior at the time of abnormality in plants, and investigate the necessity of the guide for operation procedure and the countermeasures at the time of emergency. In this explanation, the upgrading of operation training simulators which have been put already in training is discussed. The constitution of simulator system and the instructor function, the outline of PWR plant simulation models comprising thermal flow model, pump model, leak model and so on, the techniques of increasing simulator speed, and the example of analysis using the NUPAC code are reported. (K.I.)

Simulating the steam generator and the pressurizer of a PWR nuclear power plant

International Nuclear Information System (INIS)

De Greef, J.F.

1985-01-01

In a PWR nuclear power plant, considered as a power generating device, the steam generator as a subset plays an important role in the generation process, whereas the pressurizer rather acts as a control device for security purposes. Nevertheless, from a thermodynamical point of view, the two subsets behave basically in the same way, so that a common set of basic equations may be suggested to develop for each the proper mathematical simulation model. In this paper the generation of this common set of basic equations is described, from which a specific model for each device is derived. A numerical illustration of the behaviour of the two devices for typical inputs to the derived simulation model is pictured. (author)

A modular approach to modeling power plant systems

International Nuclear Information System (INIS)

Yee, N.S.

1990-01-01

This paper reports on power plants which are large, non-linear systems with numerous interactions between its component parts. In the analysis of such complex systems, dynamic simulation is recognized as a powerful method of keeping track of the myriad of interactions. A simulation can be used to answer the what if questions that are asked when replacing components, changing operational procedures, or training operators. While there are many applications for the simulation of power plant components and systems, its use is often discouraged because it can be difficult and expensive. Power plant engineering is itself a multi-disciplinary field involving fluid mechanics, heat transfer, thermodynamics, chemical engineering, nuclear engineering, and electrical engineering. Simulation requires, in addition, knowledge in model formulation, computer programming and numerical solution of differential equations

Research on engineering simulator for function validating of DCS in Nuclear Power Plant

International Nuclear Information System (INIS)

Liu Pengfei; Lin Meng; Hou Dong; Yang Yanhua; Chen Zhi

2009-01-01

An engineering simulator for the function validating of Distributed Control System in Nuclear Power Plant (NPP) was developed in this paper.In the engineering simulator, the thermal-hydraulics was modeled by Relap5, the main control system of the NPP was modeled by Matlab/Simulink, the database was built by MySQL, and the control panel was developed by the Visual Studio. NET.Data acquisition system was used to realize the real-time communication between the simulator and the real Distributed Control System in the NPP. The validating results show that the simulator can meet the requirements of validating the hardware and logic control system of DCS in NPP. (authors)

Development of experimental method to simulate the corrosion products in the primary system of nuclear power plant

International Nuclear Information System (INIS)

Kim, Sang Hyun; Kim, In Sup; Jang, Chang Heui

2005-01-01

Corrosion products are recognized as one of the major sources of occupational radiation exposure for nuclear power plant workers. Numerous studies have been conducted on the primary water chemistry to reduce the amount of crud in the primary circuit to avoid the radioactivity build-up in the plant. However, experiments with crud are restricted in laboratory because the crud is highly radioactive material. The objective of this study is to develop the simulating method of corrosion product in nuclear power plant

Requirements for a reactor simulator of the konvoi generation of nuclear power plants according to training programs

International Nuclear Information System (INIS)

Reinartz, S.J.; Reinartz, G.

1984-01-01

This report is based an a review of the literature published on simulator training and on discussions with representatives from the German nuclear power plant operator training schools. A brief description of the organisation and content of the simulator training of control room operators in a number of countries, together with a categorisation of the various types of simulators which are used. The concepts of the systems approach to training and simulator fidelity are discussed. Some general training principles which are considered important for simulator training are summarised. From the available descriptions and analyses of control room operator tasks, the skills (in most general terms) which can be trained on simulators have been identified. Methods for training these skills which are used in the simulator training programmes in various industries and which have been developed in research work in the area of training psychology have been summarised. Using these methods as a basis, the necessary instructor facilities which should be included in the design of a full simulator for the Konvoi generation of nuclear power plants have been derived. (orig.) [de

Hydraulic simulation of the systems of a nuclear power plant for charges calculation in piping

International Nuclear Information System (INIS)

Masriera, N.

1990-01-01

This work presents a general description of the methodology used by the ENACE S.A. Fluids Working Group for hydraulics simulation of a nuclear power plant system for the calculation charges in piping. (Author) [es

Simulation of the turbine trip of Unit 1 of the Laguna Verde nuclear power plant using the code Simulate-3K

International Nuclear Information System (INIS)

Alegria A, A.; Filio L, C.; Ortiz V, J.

2017-09-01

In order to compare the results obtained from the model developed in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) with the code Simulate-3K (S3K) with respect to those reported by the process computer of the Central (SIIP), the simulation of the turbine trip transient was carried out, caused by the firing of the main generator, the low differential pressure of oil of its seals and the automatic Scram of Unit 1 of the Laguna Verde nuclear power plant, at 87% of power nominal during the operation cycle 16. Since the reactor was brought to a safe stop due to Scram, was enough to simulate 20 seconds to observe the maximum increase in pressure with S3K. In this work, the following parameters are shown and compared: the neutron flux, the thermal power, the pressure in the dome, the flow at the entrance to the core, the steam flow that leaves the vessel and the minimal critical power ratio (MCPR). The neutron flux of the average power range monitors of the nuclear power plant was compared with the S3K detectors model. Finally, the MCPR was calculated with a different correlation to that of the fuel supplier and its deviation from its safety limit was determined. In conclusion, the results obtained show the current state of the model for the simulation of reactivity transients and the opportunity areas to consolidate this tool in support of the process of licensing refueling in the CNSNS. (Author)

Working in a virtual power plant

International Nuclear Information System (INIS)

Thibault, G.; Smadja, S.

1999-01-01

Graphical simulations on computer providing a virtual and reversible experience can now be used for maintenance in nuclear power plants allowing operations to be tested and tools to be optimised. Eventually, operatives will be trained to work in virtual nuclear power plants in complete safety. (authors)

Development of a compact nuclear power station engineering simulator

International Nuclear Information System (INIS)

Jian Jianfeng; Yang Yanhua; Lin Meng; Hu Rui

2003-01-01

The compact nuclear power plant project simulator is developed based on the Chashma nuclear power plant. This simulator consists of simulation computation code, data communication module and human-machine interface. This paper discusses the design and implementation of the simulator from such aspect as computer system, hydrothermal model, programming language, human-machine interface and data communication in details

Modeling and simulation of pressurizer dynamic process in PWR nuclear power plant

International Nuclear Information System (INIS)

Ma Jin; Liu Changliang; Li Shu'na

2010-01-01

By analysis of the actual operating characteristics of pressurizer in pressurized water reactor (PWR) nuclear power plant and based on some reasonable simplification and basic assumptions, the quality and energy conservation equations about pressurizer' s steam zone and the liquid zone are set up. The purpose of this paper is to build a pressurizer model of two imbalance districts. Water level and pressure control system of pressurizer is formed though model encapsulation. Dynamic simulation curves of main parameters are also shown. At last, comparisons between the theoretical analysis and simulation results show that the pressurizer model of two imbalance districts is reasonable. (authors)

Diversified types and functions and present state of the industry of nuclear power plant simulators

International Nuclear Information System (INIS)

Zanobetti, D.

1989-01-01

Nuclear plant operators must add to their class-room theoretical education a long in-plant practical training, and since the latter should include all sorts of manipulations, including those leading to accidents, it became obvious since the start of the application of nuclear energy to power production that most of the practical training should be carried out on simulators. The previous experience in flight simulation has greatly influenced the industry of nuclear simulators so that the manufacturers of large nuclear simulators have all had previous experience in the manufacture of flight trainers and simulators. Nuclear simulations come from two distinct periods: one preceding the Three Mile Island incident and one following that event which, as it has turned out to be a landmark in the development of so many aspects of the nuclear industry, has greatly influenced that of simulators. The way in which simulators are classified is first examined, and their use worldwide is discussed. (author)

Advanced modeling and simulation of integrated gasification combined cycle power plants with CO{sub 2}-capture

Energy Technology Data Exchange (ETDEWEB)

Rieger, Mathias

2014-04-17

The objective of this thesis is to provide an extensive description of the correlations in some of the most crucial sub-processes for hard coal fired IGCC with carbon capture (CC-IGCC). For this purpose, process simulation models are developed for four industrial gasification processes, the CO-shift cycle, the acid gas removal unit, the sulfur recovery process, the gas turbine, the water-/steam cycle and the air separation unit (ASU). Process simulations clarify the influence of certain boundary conditions on plant operation, performance and economics. Based on that, a comparative benchmark of CC-IGCC concepts is conducted. Furthermore, the influence of integration between the gas turbine and the ASU is analyzed in detail. The generated findings are used to develop an advanced plant configuration with improved economics. Nevertheless, IGCC power plants with carbon capture are not found to be an economically efficient power generation technology at present day boundary conditions.

Simulation-based biagnostics and control for nuclar power plants

International Nuclear Information System (INIS)

Lee, J.C.

1993-01-01

Advanced simulation-based diagnostics and control guidance systems for the identification and management of off-normal transient events in nuclear power plants is currently under investigation. To date a great deal of progress has been made in effectively and efficiently combining information obtained through fuzzy pattern recognition and macroscopic mass and energy inventory analysis for use in multiple failure diagnostics. Work has also begun on the unique problem of diagnostics and surveillance methodologies for advanced passively-safe reactors systems utilizing both statistical and fuzzy information. Plans are also being formulated for the development of deterministic optimal control algorithms combined with Monte Carlo incremental learning algorithms to be used for the flexible and efficient control of reactor transients

Simulating the Water Use of Thermoelectric Power Plants in the United States: Model Development and Verification

Science.gov (United States)

Betrie, G.; Yan, E.; Clark, C.

2016-12-01

Thermoelectric power plants use the highest amount of freshwater second to the agriculture sector. However, there is scarcity of information that characterizes the freshwater use of these plants in the United States. This could be attributed to the lack of model and data that are required to conduct analysis and gain insights. The competition for freshwater among sectors will increase in the future as the amount of freshwater gets limited due climate change and population growth. A model that makes use of less data is urgently needed to conduct analysis and identify adaptation strategies. The objectives of this study are to develop a model and simulate the water use of thermoelectric power plants in the United States. The developed model has heat-balance, climate, cooling system, and optimization modules. It computes the amount of heat rejected to the environment, estimates the quantity of heat exchanged through latent and sensible heat to the environment, and computes the amount of water required per unit generation of electricity. To verify the model, we simulated a total of 876 fossil-fired, nuclear and gas-turbine power plants with different cooling systems (CS) using 2010-2014 data obtained from Energy Information Administration. The CS includes once-through with cooling pond, once-through without cooling ponds, recirculating with induced draft and recirculating with induced draft natural draft. The results show that the model reproduced the observed water use per unit generation of electricity for the most of the power plants. It is also noticed that the model slightly overestimates the water use during the summer period when the input water temperatures are higher. We are investigating the possible reasons for the overestimation and address it in the future work. The model could be used individually or coupled to regional models to analyze various adaptation strategies and improve the water use efficiency of thermoelectric power plants.

3D Core Model for simulation of nuclear power plants: Simulation requirements, model features, and validation

International Nuclear Information System (INIS)

Zerbino, H.

1999-01-01

In 1994-1996, Thomson Training and Simulation (TT and S) earned out the D50 Project, which involved the design and construction of optimized replica simulators for one Dutch and three German Nuclear Power Plants. It was recognized early on that the faithful reproduction of the Siemens reactor control and protection systems would impose extremely stringent demands on the simulation models, particularly the Core physics and the RCS thermohydraulics. The quality of the models, and their thorough validation, were thus essential. The present paper describes the main features of the fully 3D Core model implemented by TT and S, and its extensive validation campaign, which was defined in extremely positive collaboration with the Customer and the Core Data suppliers. (author)

Power control strategy of a photovoltaic power plant for microgrid applications

Energy Technology Data Exchange (ETDEWEB)

Li, Peng [Ecole Centrale de Lille, Cite Scientifique, Villeneuve d' Ascq (FR). Laboratoire d' Electrotechnique et d' Electronique de Puissance de Lille (L2EP); Ecole Nationale Superieure d' Arts et Metiers, Lille (FR). Laboratoire d' Electrotechnique et d' Electronique de Puissance de Lille (L2EP); Francois, Bruno [Ecole Centrale de Lille, Cite Scientifique, Villeneuve d' Ascq (FR). Laboratoire d' Electrotechnique et d' Electronique de Puissance de Lille (L2EP); Degobert, Philippe [Ecole Nationale Superieure d' Arts et Metiers, Lille (FR). Laboratoire d' Electrotechnique et d' Electronique de Puissance de Lille (L2EP); Robyns, Benoit [Hautes Etudes d' Ingenieur, Lille (FR). Laboratoire d' Electrotechnique et d' Electronique de Puissance de Lille (L2EP)

2008-07-01

Photovoltaic power plants operates currently maximal power point tracking (MPPT). For microgrid applications, however, a PV power plant can not operate in the MPPT mode in all conditions. When a microgrid is islanded from the grid with few loads, a limitation of the produced power by PV plants is required and prescribed by the Distribution System Operator. This paper proposes a power control technique integrated into a dynamic model of a PV power plant by using equivalent continuous models of power electronic converters. The power limitation mode of the PV is performed by applying the correct PV terminal voltage, which corresponds to the prescribed power reference. The proposed global model is validated by simulations with the help of Matlab-Simulink trademark. (orig.)

Transient analysis models for nuclear power plants

International Nuclear Information System (INIS)

Agapito, J.R.

1981-01-01

The modelling used for the simulation of the Angra-1 start-up reactor tests, using the RETRAN computer code is presented. Three tests are simulated: a)nuclear power plant trip from 100% of power; b)great power excursions tests and c)'load swing' tests.(E.G.) [pt

Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

2000-12-15

The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

Safety in Swiss nuclear power plants

International Nuclear Information System (INIS)

Cederqvist, H.

1992-01-01

Safety-related facilities and equipment are continuously backfitted in Swiss nuclear power plants. In the Beznau-1 and -2 nuclear generating units, the measures taken under the heading of 'Backfitting of Emergency Systems' included provisions to enhance the protection against earthquakes, airplane crash, and fire; in addition, the emergency power system was upgraded. In Muehleberg, the stack exhaust air monitoring system was optimized. The containment pressure suppression system of the plant has been designed to withstand a hypothetical accident exceeding the design basis. The BKM-Crud computer simulation model simulates steps taken to reduce radiation exposure. The power of Swiss nuclear power stations will be raised by 4% to 15% within the 'Energy 2000' action program. (orig.) [de

The compact simulator for Tihange nuclear plant

International Nuclear Information System (INIS)

Gueben, M.

1982-01-01

After an introduction about the simulators for nuclear plants, a description is given of the compact simulator for the Tihange nuclear power plant as well as the simulated circuits and equipments such as the primary and secondary coolant circuits. The extent of simulation, the functions used by the instructor, the use of the simulator, the formation programme and construction planning are described. (AF)

Dynamic simulation of a sodium-cooled fast reactor power plant

Energy Technology Data Exchange (ETDEWEB)

Shinaishin, M.A.M.

1976-08-01

Simulation of the dynamic behavior of the Clinch River Breeder Reactor Plant (CRBRP) is the subject of this dissertation. The range of transients under consideration extends from a moderate transient, of the type referred to as Anticipated Transient Without Scram (ATWS), to a transient initiated by an unexpected accident followed by reactor scram. The moderate range of transients can be simulated by a digital simulator referred to as the CRBRP ATWS simulator. Two versions of this simulator were prepared; in one, the plant controllers were not included, whereas, in the other, the controllers were incorporated. A simulator referred to as the CRBRP-DCHT simulator was constructed for studying transients due to unexpected accidents followed by reactor scram. In this simulator emphasis was placed on simulating the auxiliary heat removal system, in order to determine its capability to remove the after-shut down fission and decay heat. The transients studied using the two versions of the ATWS simulator include step and ramp reactivity perturbations, and an electrical load perturbation in the controlled plant. An uncontrolled control rod withdrawal followed by reactor scram was studied using the DCHT simulator, although the duration of this transient was restricted to 20 sec. because of computer limitations. The results agree very well with the expected physical behavior of the plant.

Dynamic simulation of a sodium-cooled fast reactor power plant

International Nuclear Information System (INIS)

Shinaishin, M.A.M.

1976-08-01

Simulation of the dynamic behavior of the Clinch River Breeder Reactor Plant (CRBRP) is the subject of this dissertation. The range of transients under consideration extends from a moderate transient, of the type referred to as Anticipated Transient Without Scram (ATWS), to a transient initiated by an unexpected accident followed by reactor scram. The moderate range of transients can be simulated by a digital simulator referred to as the CRBRP ATWS simulator. Two versions of this simulator were prepared; in one, the plant controllers were not included, whereas, in the other, the controllers were incorporated. A simulator referred to as the CRBRP-DCHT simulator was constructed for studying transients due to unexpected accidents followed by reactor scram. In this simulator emphasis was placed on simulating the auxiliary heat removal system, in order to determine its capability to remove the after-shut down fission and decay heat. The transients studied using the two versions of the ATWS simulator include step and ramp reactivity perturbations, and an electrical load perturbation in the controlled plant. An uncontrolled control rod withdrawal followed by reactor scram was studied using the DCHT simulator, although the duration of this transient was restricted to 20 sec. because of computer limitations. The results agree very well with the expected physical behavior of the plant

Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant

International Nuclear Information System (INIS)

Reis Martins Junior, L.L. dos.

1980-01-01

The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author)

Interactive real-time nuclear plant simulations on a UNIX based supercomputer

International Nuclear Information System (INIS)

Behling, S.R.

1990-01-01

Interactive real-time nuclear plant simulations are critically important to train nuclear power plant engineers and operators. In addition, real-time simulations can be used to test the validity and timing of plant technical specifications and operational procedures. To accurately and confidently simulate a nuclear power plant transient in real-time, sufficient computer resources must be available. Since some important transients cannot be simulated using preprogrammed responses or non-physical models, commonly used simulation techniques may not be adequate. However, the power of a supercomputer allows one to accurately calculate the behavior of nuclear power plants even during very complex transients. Many of these transients can be calculated in real-time or quicker on the fastest supercomputers. The concept of running interactive real-time nuclear power plant transients on a supercomputer has been tested. This paper describes the architecture of the simulation program, the techniques used to establish real-time synchronization, and other issues related to the use of supercomputers in a new and potentially very important area. (author)

Annual meeting on nuclear technology '85. Technical session on nuclear power plant simulators. Jahrestagung Kerntechnik '85. Fachsitzung Simulatoren bei Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

The ten lectures read at this Technical Session deal with nuclear power plant simulators and their functions for the training of control room personnel, with test facilities for analysis and simulation of incidents and the relevant plant behaviour, and with the computer codes for fast simulation of reactor processes. The papers explain in particular the HAMMLAB project, the COSIMA fast core simulator, and the OPAL simulator for the KWU convoy process information system named PRINS.

SIROCCO project: 15 advanced instructor desk and 4 simulated control room for 900MW and 1300MW EDF power plant simulators

International Nuclear Information System (INIS)

Alphonse, J.; Roth, P.; Sicard, Y.; Rudelli, P.

2006-01-01

This presentation describes the fifteen advanced instructors station and four simulated control delivered to EDF in the frame of the SIROCCO project by the Consortium formed by ATOS Origin, CORYS Tess, for the Electricite de France (EDF). These instructor stations are installed on fifteen replica training simulators located on different sites throughout France for the purposes of improving the job-related training of the EDF PWR nuclear power plant operating teams. This covers all 900 MW and 1300MW nuclear power plant of EDF. The simulated control rooms are installed on maintenance platform located at EDF and the consortium facilities. The consortium uses it to maintain and upgrade the simulators. EDF uses it to validate the upgrade delivered by the consortium before on site installation and to perform engineering analysis. This presentation sets out successively: - The major advantages of the generic and configurable connected module concept for flexible and quick adaptation to different simulators; - The innovative functionalities of the advanced Instructor Desk (IS) which make the instructor's tasks of preparation, monitoring and postanalysis of a training session easier and more homogeneous; - The use of the Simulated Control Room (SCR) for training purposes but also for those of maintenance and design studies for upgrades of existing control rooms

Application of simulation techniques for accident management training in nuclear power plants

International Nuclear Information System (INIS)

2003-05-01

core. These capabilities include the optimized use of design margins as well as complementary measures for the prevention of accident progression, its monitoring, and the mitigation of severe accidents. Finally, level 5 includes off-site emergency response measures, the objective of which is to mitigate the radiological consequences of significant releases of radioactive material. Accident management is defined in the IAEA Safety Report on Development and Implementation of Accident Management Programmes in Nuclear Power Plants. The IAEA definitions are in line with the definitions of severe accident management in OECD/NEA documents as given, for example. This report describes simulation techniques used in the training of personnel involved in accident management of NPPs. This concerns both the plant personnel and the persons involved in the management of off-site releases. The report pertains to light water reactors (LWRs) and pressurized heavy water reactors (PHWRs), but it can equally be applied to power reactors of other types. The report is intended for use by experts responsible for planning, developing, executing or supervising the training of personnel involved in the implementation of AMPs in NPPs. It concentrates on existing techniques, but future prospects are also discussed. Various simulation techniques are considered, from incorporating graphical interfaces into existing severe accident codes to full-scope replica simulators. Both preventive and mitigative accident management measures, different training levels and different target personnel groups are taken into account. Based on the available information compiled worldwide, present views on the applicability of simulation techniques for the training of personnel involved in accident management are provided in this report. Apart from the introduction, this report consists of four sections and three appendices. In Section 2, specific aspects of accident management are summarized. Basic approaches in the

Process simulation of heavy water plants - a powerful analytical tool

International Nuclear Information System (INIS)

Miller, A.I.

1978-10-01

The commercially conscious designs of Canadian GS (Girdler-Sulphide) have proved sensitive to process conditions. That, combined with the large scale of our units, has meant that computer simulation of their behaviour has been a natural and profitable development. Atomic Energy of Canada Limited has developed a family of steady state simulations to describe all of the Canadian plants. Modelling of plant conditions has demonstrated that the simulation description is very precise and it has become an integral part of the industry's assessments of both plant operation and decisions on capital expenditures. The simulation technique has also found extensive use in detailed designing of both the rehabilitated Glace Bay and the new La Prade plants. It has opened new insights into plant design and uncovered a radical and significant flowsheet change for future designs as well as many less dramatic but valuable lesser changes. (author)

Dynamic modeling of IGCC power plants

International Nuclear Information System (INIS)

Casella, F.; Colonna, P.

2012-01-01

Integrated Gasification Combined Cycle (IGCC) power plants are an effective option to reduce emissions and implement carbon-dioxide sequestration. The combination of a very complex fuel-processing plant and a combined cycle power station leads to challenging problems as far as dynamic operation is concerned. Dynamic performance is extremely relevant because recent developments in the electricity market push toward an ever more flexible and varying operation of power plants. A dynamic model of the entire system and models of its sub-systems are indispensable tools in order to perform computer simulations aimed at process and control design. This paper presents the development of the lumped-parameters dynamic model of an entrained-flow gasifier, with special emphasis on the modeling approach. The model is implemented into software by means of the Modelica language and validated by comparison with one set of data related to the steady operation of the gasifier of the Buggenum power station in the Netherlands. Furthermore, in order to demonstrate the potential of the proposed modeling approach and the use of simulation for control design purposes, a complete model of an exemplary IGCC power plant, including its control system, has been developed, by re-using existing models of combined cycle plant components; the results of a load dispatch ramp simulation are presented and shortly discussed. - Highlights: ► The acausal dynamic model of an entrained gasifier has been developed. ► The model can be used to perform system optimization and control studies. ► The model has been validated using field data. ► Model use is illustrated with an example showing the transient of an IGCC plant.

Human factors in nuclear power plants

International Nuclear Information System (INIS)

Pack, R.W.

1978-01-01

The Electric Power Research Institute has started research in human factors in nuclear power plants. One project, completed in March 1977, reviewed human factors problems in operating power plants and produced a report evaluating those problems. A second project developed computer programs for evaluating operator performance on training simulators. A third project is developing and evaluating control-room design approaches. A fourth project is reviewing human factors problems associated with power-plant maintainability and instrumentation and control technician activities. Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. The Electric Power Research Institute (EPRI) has undertaken four projects studying the application of human factors engineering principles to nuclear power plants. (author)

EPRI compact analyzer: A compact, interactive and color-graphics based simulator for power plant analysis

International Nuclear Information System (INIS)

Ipakchi, A.; Khadem, M.; Chen, H.; Colley, R.W.

1986-01-01

This paper presents the results of an EPRI sponsored project (RP2395-2) for design and development of an interactive, and color graphics based simulator for power plant analysis. The system is called Compact Analyzer and can be applied to engineering and training applications in the utility industry. The Compact Analyzer's software and system design are described. Results of two demonstration system for a nuclear plant, and a fossil plant are presented, and the applications of the Compact Analyzer to operating procedures evaluation are discussed

Modelling and simulation of thermal power plants

Energy Technology Data Exchange (ETDEWEB)

Eborn, J.

1998-02-01

Mathematical modelling and simulation are important tools when dealing with engineering systems that today are becoming increasingly more complex. Integrated production and recycling of materials are trends that give rise to heterogenous systems, which are difficult to handle within one area of expertise. Model libraries are an excellent way to package engineering knowledge of systems and units to be reused by those who are not experts in modelling. Many commercial packages provide good model libraries, but they are usually domain-specific and closed. Heterogenous, multi-domain systems requires open model libraries written in general purpose modelling languages. This thesis describes a model database for thermal power plants written in the object-oriented modelling language OMOLA. The models are based on first principles. Subunits describe volumes with pressure and enthalpy dynamics and flows of heat or different media. The subunits are used to build basic units such as pumps, valves and heat exchangers which can be used to build system models. Several applications are described; a heat recovery steam generator, equipment for juice blending, steam generation in a sulphuric acid plant and a condensing steam plate heat exchanger. Model libraries for industrial use must be validated against measured data. The thesis describes how parameter estimation methods can be used for model validation. Results from a case-study on parameter optimization of a non-linear drum boiler model show how the technique can be used 32 refs, 21 figs

Loviisa nuclear power plant analyzer

International Nuclear Information System (INIS)

Porkholm, K.; Nurmilaukas, P.; Tiihonen, O.; Haenninen, M.; Puska, E.

1992-12-01

The APROS Simulation Environment has been developed since 1986 by Imatran Voima Oy (IVO) and the Technical Research Centre of Finland (VTT). It provides tools, solution algorithms and process components for use in different simulation systems for design, analysis and training purposes. One of its main nuclear applications is the Loviisa Nuclear Power Plant Analyzer (LPA). The Loviisa Plant Analyzer includes all the important plant components both in the primary and in the secondary circuits. In addition, all the main control systems, the protection system and the high voltage electrical systems are included. (orig.)

Simulation analysis of emissions trading impact on a non-utility power plant

International Nuclear Information System (INIS)

Imran, Kashif; Ahmad, Intesar; Hassan, Tehzeebul; Aslam, Muhammad Farooq; Ngan, Hon-Wing

2009-01-01

Non-utility power plants can competitively participate in open electricity market to reduce operational costs but in the absence of pollution charges or emissions trading such generators are tempted to cause greater pollution for profit maximization. This paper presents a solution that incorporates pollution charges for nitrogen oxides and sulphur dioxide emissions in line with existing national environmental quality standards and a new carbon dioxide emissions trading mechanism. A novel approach has been used for allocation of allowable emissions that favors efficiently fuelled and environmentally friendly operation for maximizing profit. Impact of proposed carbon trading on economical utilization of enormous indigenous coal reserves has been analyzed and determined to be acceptable. Software developed in this paper, harnessing Sequential Quadratic Programming capabilities of Matlab, is shown to be adequate simulation tool for various emissions trading schemes and an useful operational decision making tool for constrained non-linear optimization problem of a non-utility power plant. (author)

Simulation analysis of emissions trading impact on a non-utility power plant

Energy Technology Data Exchange (ETDEWEB)

Imran, Kashif; Ahmad, Intesar [Department of Electrical Engineering, COMSATS Institute of IT, Lahore (Pakistan); Hassan, Tehzeebul [Department of Electrical Engineering, University of Engineering and Technology (UET), Lahore (Pakistan); Aslam, Muhammad Farooq [Department of Electrical Engineering, University of Management and Technology (UMT), Lahore (Pakistan); Ngan, Hon-Wing [Department of Electrical Engineering, Hong Kong Polytechnic University (China)

2009-12-15

Non-utility power plants can competitively participate in open electricity market to reduce operational costs but in the absence of pollution charges or emissions trading such generators are tempted to cause greater pollution for profit maximization. This paper presents a solution that incorporates pollution charges for nitrogen oxides and sulphur dioxide emissions in line with existing national environmental quality standards and a new carbon dioxide emissions trading mechanism. A novel approach has been used for allocation of allowable emissions that favors efficiently fuelled and environmentally friendly operation for maximizing profit. Impact of proposed carbon trading on economical utilization of enormous indigenous coal reserves has been analyzed and determined to be acceptable. Software developed in this paper, harnessing Sequential Quadratic Programming capabilities of Matlab, is shown to be adequate simulation tool for various emissions trading schemes and an useful operational decision making tool for constrained non-linear optimization problem of a non-utility power plant. (author)

Hardware-in-the-loop (HIL) nuclear power plant training simulation platform design and validation

Energy Technology Data Exchange (ETDEWEB)

Rankin, D.J. [Univ. of Western Ontario, Control and Instrumentation (CIES) Research Group, Dept. of Electrical and Computer Engineering, London, Ontario (Canada)

2008-07-01

The design, development and validation of a hardware-in- the-loop (HIL) simulation platform are presented. An Invensys Triconex Tricon v9 safety PLC is interfaced to a nuclear power plant (NPP) simulation suite, replicating the operation of Darlington NPP. Communication between the simulator and external hardware is supported by a National Instruments (NI) data acquisition system (DAQ) and a customized virtual instrument (VI). Event timings within the control loop are thoroughly investigated and an acceptable method for HIL platform communication is developed. A sample application (primary shutdown system (SDS1)) is implemented and evaluated. SDS1 evaluation is performed with focus on steam generator (SG) level low trip scenarios. For this purpose, a design basis accident (DBA) associated with SDS1 regulatory standards is applied to the HIL simulation environment and compared with simulated expected plant operation. Further, the role of the Tricon v9 system within the HIL loop is investigated to establish a basis for the future integration of the entire SDS1 control logic. (author)

HVDC transmission from isorated nuclear power plant

International Nuclear Information System (INIS)

Takenaka, Kiyoshi; Takasaki, Masahiro; Ichikawa, Tatemi; Hayashi, Toshiyuki

1985-01-01

HVDC transmission directly from nuclear power plant is considered as one of the patterns of long distance and large capacity transmission system. This reports considers two route HVDC transmission from PWR type nuclear power plant, and analyzes dynamic response characteristics due to bus fault, main protection failure and etc. using the AC-DC Power System Simulator. (author)

Knowledge-enhanced network simulation modeling of the nuclear power plant operator

International Nuclear Information System (INIS)

Schryver, J.C.; Palko, L.E.

1988-01-01

Simulation models of the human operator of advanced control systems must provide an adequate account of the cognitive processes required to control these systems. The Integrated Reactor Operator/System (INTEROPS) prototype model was developed at Oak Ridge National Laboratory (ORNL) to demonstrate the feasibility of dynamically integrating a cognitive operator model and a continuous plant process model (ARIES-P) to provide predictions of the total response of a nuclear power plant during upset/emergency conditions. The model consists of a SAINT network of cognitive tasks enhanced with expertise provided by a knowledge-based fault diagnosis model. The INTEROPS prototype has been implemented in both closed and open loop modes. The prototype model is shown to be cognitively relevant by accounting for cognitive tunneling, confirmation bias, evidence chunking, intentional error, and forgetting

Modeling of a combined cycle power plant

International Nuclear Information System (INIS)

Faridah Mohamad Idris

2001-01-01

The combined cycle power plant is a non-linear, closed loop system, which consists of high-pressure (HP) superheater, HP evaporator, HP economizer, low-pressure (LP) evaporator, HP drum, HP deaerator, condenser, HP and LP steam turbine and gas turbine. The two types of turbines in the plant for example the gas turbine and the HP and LP steam turbines operate concurrently to generate power to the plant. The exhaust gas which originate from the combustion chamber drives the gas turbine, after which it flows into the heat recovery steam generator (HRSG) to generate superheated steam to be used in driving the HP and LP steam turbines. In this thesis, the combined cycle power plant is modeled at component level using the physical method. Assuming that there is delay in transport, except for the gas turbine system, the mass and heat balances are applied on the components of the plant to derive the governing equations of the components. These time dependent equations, which are of first order differential types, are then solved for the mass and enthalpy of the components. The solutions were simulated using Matlab Simulink using measured plant data. Where necessary there is no plant data available, approximated data were used. The generalized regression neural networks are also used to generate extra sets of simulation data for the HRSG system. Comparisons of the simulation results with its corresponding plant data showed good agreements between the two and indicated that the models developed for the components could be used to represent the combined cycle power plant under study. (author)

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.)

Virtual control desk for operators training: a case study for a nuclear power plant simulator

International Nuclear Information System (INIS)

Aghina, Mauricio Alves da Cunha e

2009-03-01

Nuclear Power Plant (NPP) is a facility for electrical energy generation. Because of its high degree of complexity and very rigid norms of security it is extremely necessary that operators are very well trained for the NPP operation. A mistaken operation by a human operator may cause a shutdown of the NPP, incurring in a huge economical damage for the owner and for the population in the case of a electric net black out. To reduce the possibility of a mistaken operation, the NPP usually have a full scope simulator of the plant's control room, which is the physical copy of the original control room. The control of this simulator is a computer program that can generate the equal functioning of the normal one or some scenarios of accidents to train the operators in many abnormal conditions of the plant. A physical copy of the control room has a high cost for its construction, not only of its facilities but also for its physical components. The proposal of this work is to present a project of a virtual simulator with the modeling in 3D stereo of a control room of a given nuclear plant with the same operation functions of the original simulator. This virtual simulator will have a lower cost and serves for pretraining of operators with the intention of making them familiar to the original control room. (author)

Technical study of real-time simulation system for digital I and C system of steam generator in nuclear power plant

International Nuclear Information System (INIS)

Shi Ji; Jiang Mingyu; Ma Yunqin

2004-01-01

The real-time simulation system, which forms a interactive closed circle together with the steam generator control system, has been developed using a dynamic mathematical model of steam generator in this paper. It can provide a simulation target for upgrades of digital Instrument and Control system in Nuclear Power Plant (NPP) and is applicable for further research of control schemes. With this program, the authors have studied and analyzed the response of transient parameters to some different disturbance, the calculated results are in good agreement with those calculated by NPP simulator program. This will give a theoretical analysis for upgrades of digital I and C system in nuclear power plant

D1+ Simulator: A cost and risk optimized approach to nuclear power plant simulator modernization

International Nuclear Information System (INIS)

Wischert, W.

2006-01-01

D1-Simulator is operated by Kraftwerks-Simulator-Gesellschaft (KSG) and Gesellschaft f?r Simulatorschulung (GfS) at the Simulator Centre in Essen since 1977. The full-scope control room training simulator, used for Kernkraftwerk Biblis (KWB) is based on a PDP-11 hardware platform and is mainly programmed in ASSEMBLER language. The Simulator has reached a continuous high availability of operation throughout the years due to specialized hardware and software support from KSG maintenance team. Nevertheless, D1-Simulator largely reveals limitations with respect to computer capacity and spares and suffers progressively from the non-availability of hardware replacement materials. In order to ensure long term maintainability within the framework of the consensus on nuclear energy, a 2-years refurbishing program has been launched by KWB focusing on quality and budgetary aspects. The so-called D1+ Simulator project is based on the re-use of validated data from existing simulators. Allowing for flexible project management methods, the project outlines a cost and risk optimized approach to Nuclear Power Plant (NPP) Simulator modernization. D1+ Simulator is being built by KSG/GfS in close collaboration with KWB and the simulator vendor THALES by re-using a modern hardware and software development environment from D56-Simulator, used by Kernkraftwerk Obrigheim (KWO) before its decommissioning in 2005. The Simulator project, launched in 2004, is expected to be completed by end of 2006. (author)

BRENDA: a dynamic simulator for a sodium-cooled fast reactor power plant

International Nuclear Information System (INIS)

Hetrick, D.L.; Sowers, G.W.

1978-06-01

This report is a users' manual for one version of BRENDA (Breeder Reactor Nuclear Dynamic Analysis), which is a digital program for simulating the dynamic behavior of a sodium-cooled fast reactor power plant. This version, which contains 57 differential equations, represents a simplified model of the Clinch River Breeder Reactor Project (CRBRP). BRENDA is an input deck for DARE P (Differential Analyzer Replacement, Portable), which is a continuous-system simulation language developed at the University of Arizona. This report contains brief descriptions of DARE P and BRENDA, instructions for using BRENDA in conjunction with DARE P, and some sample output. A list of variable names and a listing for BRENDA are included as appendices

Development of a Desktop Simulator for APR1400 Nuclear Power Plant

International Nuclear Information System (INIS)

Lee, J. B.

2016-01-01

It is essential for utilities to possess a full-scope simulator for operator training and operation test for operators. But it is very expensive and sometimes lack of fidelity if processes of developing the simulator and designing the plant are in parallel. It is due to the situation that simulator development stage sometimes precedes the plant design stage and modifications may occur to the design of the plant in construction stage. In an attempt to build a low cost and efficient simulator, a desktop simulator has been developed. This model is described herein. Using desktop simulators for training operators is an efficient method for familiarizing operators with their plant’s operation. A low cost and efficient desktop simulator for APR1400 has been developed, and brief features are introduced here. It is configured to mimic a full-scale simulator, and can be used for operators to be familiarized to their plant’s operation. Since the size of the simulator is small enough to be fit in a desk, it can be used in a classroom or in an office at any time. It can also be used to evaluate design changes or modifications of the plant before implementing them to the plant

Development of a Desktop Simulator for APR1400 Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Lee, J. B. [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2016-10-15

It is essential for utilities to possess a full-scope simulator for operator training and operation test for operators. But it is very expensive and sometimes lack of fidelity if processes of developing the simulator and designing the plant are in parallel. It is due to the situation that simulator development stage sometimes precedes the plant design stage and modifications may occur to the design of the plant in construction stage. In an attempt to build a low cost and efficient simulator, a desktop simulator has been developed. This model is described herein. Using desktop simulators for training operators is an efficient method for familiarizing operators with their plant’s operation. A low cost and efficient desktop simulator for APR1400 has been developed, and brief features are introduced here. It is configured to mimic a full-scale simulator, and can be used for operators to be familiarized to their plant’s operation. Since the size of the simulator is small enough to be fit in a desk, it can be used in a classroom or in an office at any time. It can also be used to evaluate design changes or modifications of the plant before implementing them to the plant.

Model and simulation of the hydraulic turbine speed regulator of the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Copparoni, G.; Etchepareborda, A.; Urrutia, G.

1992-01-01

The hydraulics turbines of Atucha I Nuclear Power Plant takes advantage of condenser cooling water level difference between the plant and the river to recover about 2,5 MW e. It also supplies emergency power until diesel generators start up. Speed regulation is needed due to the transients that during this process occur. The purpose is to minimize the diesels start up time, and to avoid overshoots on the internal grid frequency. The hydraulic turbine, its speed regulator and the electric system associated with this transient have been modeled. The models and some simulation results are presented in this work. (author)

Manpower development for safe operation of nuclear power plant. China. Simulator software development. UNDP-Activity: 2.1.8-IAEA-Task-01. Technical report

International Nuclear Information System (INIS)

Feng, C.P.

1994-01-01

In the frameworks of the project ''manpower development for safe operation of nuclear power plant'' the development of reactor simulator software is described. Qinshan nuclear power plant was chosen as a reference one

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)

Modeling of the wind power plant using software DIgSILENT Power factory

International Nuclear Information System (INIS)

Mladenovski, Ljubisha; Iliev, Atanas; Fushtikj, Vangel

2004-01-01

This paper presents a method for creating a model of the wind power plant NORDEX N-60 in the DIgSILENT Power factory software. At the beginning, the characteristics of the wind power plant and the used software are shortly described. The next step is modeling the part of the power system where the wind power plant will be connected to the grid The modeling of the turbine part and the generator part of the wind power plant is made with blocks, which are part of the machine block of the composite model. Finally, the results obtained from performed practically oriented simulations are presented in graphical form. Design of the model of the wind power plant NORDEX N-60 was performed at the Faculty of Electrical Engineering, at the University of Rostock, Germany, as a part of the DYSIMAC project. (Author)

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)

Development of the simulation system {open_quotes}IMPACT{close_quotes} for analysis of nuclear power plant severe accidents

Energy Technology Data Exchange (ETDEWEB)

Naitoh, Masanori; Ujita, Hiroshi; Nagumo, Hiroichi [Nuclear Power Corp. (Japan)] [and others

1997-07-01

The Nuclear Power Engineering Corporation (NUPEC) has initiated a long-term program to develop the simulation system {open_quotes}IMPACT{close_quotes} for analysis of hypothetical severe accidents in nuclear power plants. IMPACT employs advanced methods of physical modeling and numerical computation, and can simulate a wide spectrum of senarios ranging from normal operation to hypothetical, beyond-design-basis-accident events. Designed as a large-scale system of interconnected, hierarchical modules, IMPACT`s distinguishing features include mechanistic models based on first principles and high speed simulation on parallel processing computers. The present plan is a ten-year program starting from 1993, consisting of the initial one-year of preparatory work followed by three technical phases: Phase-1 for development of a prototype system; Phase-2 for completion of the simulation system, incorporating new achievements from basic studies; and Phase-3 for refinement through extensive verification and validation against test results and available real plant data.

Development of new NSSS thermal-hydraulic model for Korean standard nuclear power plant(UCN-3/4) simulator

International Nuclear Information System (INIS)

Kim, Kyung Doo; Jeong, Jae Jun

2001-09-01

The NSSS thermal-hydraulic programs installed in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually adopt very simplified physical models for a real-time simulation of NSSS thermal-hydraulic phenomena, which entails inaccurate results and the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, we developed a realistic NSSS T/H program (named 'ARTS-UCN' code) for the improvement of the Korean Standard Nuclear Power Plant full-scope simulator. ARTS Code, developed as an NSSS T/H model for the KNPEC no. 2 simulator using the RETRAN03 code, was selected as a reference code for ARTS-UCN code development. For the development of ARTS, the followings have been performed: - Improvement of the robustness of RETRAN - Improvement of the real-time simulation capability of RETRAN - Optimum input data generation for the NSSS simulation - New model development that cannot be efficiently modeled by RETRAN - Assessment of the ARTS code. The systematic assessment of ARTS has been conducted in both personal computers (Windows 98, Visual fortran) and the simulator development environment (Windows NT, GSE simulator development tool). The results were resonable in terms of accuracy, real-time simulation and robustness

Experiment research on cognition reliability model of nuclear power plant

International Nuclear Information System (INIS)

Zhao Bingquan; Fang Xiang

1999-01-01

The objective of the paper is to improve the reliability of operation on real nuclear power plant of operators through the simulation research to the cognition reliability of nuclear power plant operators. The research method of the paper is to make use of simulator of nuclear power plant as research platform, to take present international research model of reliability of human cognition based on three-parameter Weibull distribution for reference, to develop and get the research model of Chinese nuclear power plant operators based on two-parameter Weibull distribution. By making use of two-parameter Weibull distribution research model of cognition reliability, the experiments about the cognition reliability of nuclear power plant operators have been done. Compared with the results of other countries such USA and Hungary, the same results can be obtained, which can do good to the safety operation of nuclear power plant

Probabilistic production simulation including CHP plants

Energy Technology Data Exchange (ETDEWEB)

Larsen, H.V.; Palsson, H.; Ravn, H.F.

1997-04-01

A probabilistic production simulation method is presented for an energy system containing combined heat and power plants. The method permits incorporation of stochastic failures (forced outages) of the plants and is well suited for analysis of the dimensioning of the system, that is, for finding the appropriate types and capacities of production plants in relation to expansion planning. The method is in the tradition of similar approaches for the analysis of power systems, based on the load duration curve. The present method extends on this by considering a two-dimensional load duration curve where the two dimensions represent heat and power. The method permits the analysis of a combined heat and power system which includes all the basic relevant types of plants, viz., condensing plants, back pressure plants, extraction plants and heat plants. The focus of the method is on the situation where the heat side has priority. This implies that on the power side there may be imbalances between demand and production. The method permits quantification of the expected power overflow, the expected unserviced power demand, and the expected unserviced heat demand. It is shown that a discretization method as well as double Fourier series may be applied in algorithms based on the method. (au) 1 tab., 28 ills., 21 refs.

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.

Vibrations of wind power plants; Schwingungen von Windenergieanlagen

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

means of a multi-component simulation and the finite element method (B. Schlecht, T. Rosenloechre, T. Schulze); (15) Impact of modelling on the simulation of the dynamics of the powertrain at wind power plants (T. Hecquet, S. Hauptmann, M. Kuehn, B. Marrant, J. Peeters, K. Smolders, J. Schwarte, F. Stache); (16) Aeroelastic rotors in the multi-component simulation (R. Schelenz, S. Flock, D. Moeller); (17) Investigations at hybrid tower constructions of wind power plants (J. Gruenberg, M. Hansen, S. Kromminga); (18) Vibration behaviour of pile founded wind power plants (J. Grabe, S. Henke, J. Duehrkop); (19) Operation behaviour and vibration behaviour of a powertrain of wind power plants (T. Gellermann); (20) Technical and financial results of a 5 years of condition monitoring on 8 wind turbines farm (F. Fugon, F. Wery); (21) Interactions of unbalanced states during the operation of a wind power plant and impact on the lifetime of all components (J. Holling, M. Bergmann); (22) Vibration dampers in wind power plants (T. Schumacher); (23) Advanced analysis of sensory data yields focused fault indications for industrial machinery, electrical power systems, and physical infrastructure (P. Johnson); (24) Connecting elements for wind power plants with enhanced vibration resistance (U. Hasselmann, T. Braun); (25) FMEA based vibration monitoring of wind power plants (J. Loesl, E. Becker); (26) Counterbalancing of generators at wind power plants (D. Franke, G. Schmidt); (27) Geotechnical measurements of the interaction surface-monopile at FINO (J. Gattermann, U. Berndt, J. Stahlmann); (28) APSOvib registered - tailor-made elastomer bearing for wind power plants (R. Eberlein).

Plant simulators using gateway devices

International Nuclear Information System (INIS)

Forbes, H.W.

1988-01-01

One of the most difficult tasks in building a full-scope power plant simulator is modelling the plant process computer. For reasons of cost, it is usually not feasible to include a duplicate process computer within the simulator, although this would provide the highest degree of realism. The recent introduction of gateway devices by several process control manufacturers changes the cost picture considerably. These gateways are capable of emulating Input/Output multiplexers and controllers at significantly less cost. Simulators which use these devices can provide the absolute realism of a duplicate process computer without the associated cost burden. This paper discusses the use of gateways in simulators, and examines the case of a simulator now being built which uses this design technique

A method for analysis of nuclear power plant operators' decision making in simulated disturbance situations

International Nuclear Information System (INIS)

1995-01-01

An analysis method has been developed for analysis of nuclear power plant operators' decision making in simulated disturbance situations. The aim of the analysis is to investigate operators' orientation which is expected to manifest itself as collective strategies in utilization of resources of decision making. Resources analyzed here are different information sources and, in addition, collaborative resources like communication and participation. The cognitive approach on the basis of the method considers decision making as collective construction of common interpretation of available information. Utilization of information is evaluated with respect to operative context. This is made with help of conceptualization of the disturbance situation from the decision making point of view and by construction of operative reference for activity. The latter means conceptualization of the situation from the safety point of view and also consideration of other boundary constraints of decision making, i.e. economical and technical aspects. The analysis method is intended to be used in routine simulator training in nuclear power plants. By virtue of its contextual and dynamical approach it makes the developing nature of activity visible. Cumulation and distribution of knowledge of decision making as developing activity, controlled by orientation and boundary constraints of process control, is expected to improve operational culture of a plant organization. (author). 2 refs, 1 fig

Limitation of fusion power plant installation on future power grids under the effect of renewable and nuclear power sources

Energy Technology Data Exchange (ETDEWEB)

Takeda, Shutaro, E-mail: takeda.shutarou.55r@st.kyoto-u.ac.jp [Graduate School of Advanced Integrated Studies in Human Survivability, Kyoto University, Kyoto, Kyoto (Japan); Sakurai, Shigeki [Graduate School of Advanced Integrated Studies in Human Survivability, Kyoto University, Kyoto, Kyoto (Japan); Yamamoto, Yasushi [Faculty of Engineering Science, Kansai University, Suita, Osaka (Japan); Kasada, Ryuta; Konishi, Satoshi [Institute of Advanced Energy, Kyoto University, Uji, Kyoto (Japan)

2016-11-01

Graphical abstract: - Highlights: • Future power grids would be unstable due to renewable and nuclear power sources. • Output interruptions of fusion plant would cause disturbances to future grids. • Simulation results suggested they would create limitations in fusion installation. • A novel diagram was presented to illustrate this suggested limitation. - Abstract: Future power grids would be unstable because of the larger share of renewable and nuclear power sources. This instability might bring some additional difficulties to fusion plant installation. Therefore, the authors carried out a quantitative feasibility study from the aspect of grid stability through simulation. Results showed that the more renewable and nuclear sources are linked to a grid, the greater disturbance the grid experiences upon a sudden output interruption of a fusion power plant, e.g. plasma disruption. The frequency deviations surpassed 0.2 Hz on some grids, suggesting potential limitations of fusion plant installation on future grids. To clearly show the suggested limitations of fusion plant installations, a novel diagram was presented.

Comparison of simulated and measured response of load rejection on A hydro power plant model with mixed mode nonlinear controller

Energy Technology Data Exchange (ETDEWEB)

Babunski, Darko; Tuneski, Atanasko; Zaev, Emil [Faculty of Mechanical Engineering, ' Ss. Cyril and Methodius' University, Skopje (Macedonia, The Former Yugoslav Republic of)

2014-07-01

Revised Hydro Power Plant model of the IEEE working group recommended converted to state space model is used for simulation of transient response of hydro turbine, and verification was made using measurements of transients from real Hydro Power Plant (HPP). Nonlinear mixed model controller was designed and implemented into complete HPP simulation model and compared with PID with real parameters used in HPP, and with adjusted PID parameters with consideration of smallest frequency error. Verification of performance of the model was made comparing model response with measured load rejection, which is worst case of HPP operation. (Author)

Study on optimization of normal plant outage work plan for nuclear power plants

International Nuclear Information System (INIS)

Aoki, Takayuki; Kodama, Noriko; Takase, Kentaro; Miya, Kenzo

2011-01-01

This paper discusses maintenance optimization in maintenance implementation stage following maintenance planning stage in nuclear power plants and proposes a methodology to get an optimum maintenance work plan. As a result of consideration, the followings were obtained. (1) The quantitative evaluation methodology for optimizing maintenance work plan in nuclear power plants was developed. (2) Utilizing the above methodology, a simulation analysis of maintenance work planning for BWR's PLR and RHR systems in a normal plant outage was performed. Maintenance cost calculation in several cases was carried out on the condition of smoothening man loading over the plant outage schedule as much as possible. (3) As a result of the simulation, the economical work plans having a flat man loading over the plant outage schedule were obtained. (author)

Model Predictive Control of Integrated Gasification Combined Cycle Power Plants

Energy Technology Data Exchange (ETDEWEB)

B. Wayne Bequette; Priyadarshi Mahapatra

2010-08-31

The primary project objectives were to understand how the process design of an integrated gasification combined cycle (IGCC) power plant affects the dynamic operability and controllability of the process. Steady-state and dynamic simulation models were developed to predict the process behavior during typical transients that occur in plant operation. Advanced control strategies were developed to improve the ability of the process to follow changes in the power load demand, and to improve performance during transitions between power levels. Another objective of the proposed work was to educate graduate and undergraduate students in the application of process systems and control to coal technology. Educational materials were developed for use in engineering courses to further broaden this exposure to many students. ASPENTECH software was used to perform steady-state and dynamic simulations of an IGCC power plant. Linear systems analysis techniques were used to assess the steady-state and dynamic operability of the power plant under various plant operating conditions. Model predictive control (MPC) strategies were developed to improve the dynamic operation of the power plants. MATLAB and SIMULINK software were used for systems analysis and control system design, and the SIMULINK functionality in ASPEN DYNAMICS was used to test the control strategies on the simulated process. Project funds were used to support a Ph.D. student to receive education and training in coal technology and the application of modeling and simulation techniques.

Method and system for nuclear power plant synchroscope simulation for operator training

International Nuclear Information System (INIS)

Alliston, W.H.; Johnson, S.J.

1975-01-01

A method and system are described for the real--time simulation of the dynamic operation of a nuclear power plant in which a synchroscope is provided for determining the frequency and phase difference of two voltage sources for informing the operator of the proper conditions for connecting the two voltage sources to a common electrical distribution line. A digital computer means is used for calculating data relating to the frequency difference between combinations of two voltage sources in accordance with predetermined simulated conditions including the operation of control panel devices. A digital to analogue converter utilizes the selected frequency difference and a bias factor to operate a voltage controlled generator for producing an AC voltage which operates a synchroscope dial in accordance with its frequency and the frequency of a constant reference voltage. (Official Gazette)

Numerical simulation of nuclear power plants on multiprocessor systems

International Nuclear Information System (INIS)

Boeer, R.; Finnemann, H.; Mueller, R.; Krapf, J.

1990-04-01

The present final report gives an account of work performed and results obtained at Siemens/KWU within the frame of SUPRENUM project. The coupled neutron kinetics - thermal hydraulics program system 3D-SIM for the calculation of steady-state and transient conditions in the core and in the coolant loops of light water reactors has been developed. Making efficient use of the parallel computing architecture required the implementation of novel, purpose-built software concepts which can be characterized by multigrid algorithms and parallelization by domain decomposition. The modules treating the reactor core are 3D-NEUT for neutron kinetics and 3D-THERM for thermal hydraulics, the remaining system and control components being represented by the module NLOOP. This modular structure is a main feature of 3D-SIM which allows a flexible choice of applications, employing modules individually or in combinations to fulfil a specific calculation task. In particular, 3D-SIM reactor core representation is fully 3-dimensional for both neutron diffusion and thermal-hydraulic equations, allowing coupled calculations and evaluation of crossflow between fuel elements or subchannels. Including also the loops and plant models, 3D-SIM is a powerful analytical tool for simulating pressurized plant response to a wide spectrum of events. (orig.) With 25 refs., 11 figs [de

Three-dimensional simulation of radioactive pollutant in the atmosphere from nuclear power plant

International Nuclear Information System (INIS)

Buske, Daniela; Vilhena, Marco Tullio de

2008-01-01

In this work we report numerical simulations using the GILTT (Generalized Integral Laplace Transform Technique) approach to simulate radioactive pollutant dispersion in the Planetary Boundary Layer (PBL). To study the dispersion and the possible scenarios arising from accidental emissions, the results obtained with the GILTT method are compared with experimental data obtained at the Nuclear Power Plant of Angra dos Reis under neutral/moderately unstable conditions. Furthermore, to a better description of the wind profile for the irregular ground level terrain, we consider the wind profile as solution of the MM5 mesoscale model. The statistical indices point out a reasonable good agreement is obtained between experimental data and GILTT model. (author)

Simulation of hanging dams downstream of Ossauskoski power plant

Energy Technology Data Exchange (ETDEWEB)

Aaltonen, J.; Huokuna, M. [Finnish Environment Inst., Helsinki (Finland); Severinkangas, K.; Talvensaari, M. [Kemijoki Oy, Rovaniemi (Finland)

2008-07-01

Sixteen power plants have been constructed along Finland's Kemijoki River for hydroelectric power production. The Ossauskoski facility has recently undergone major renovations and upgrade, making it the sixth largest hydroelectric power plant in Finland, with a new capacity of 124 MW and an annual energy output of 501 GWh. The increase in power output and discharge may cause changes in ice conditions downstream of the power plant. The section of the river is already subjected to frazil ice problems and hanging dam formation. Discharges and adverse effects of frazil ice phenomena are likely to increase due to climate change, resulting in harm for hydropower production and the environment, particularly in flow regulated rivers where winter discharges are higher than natural discharges. As such, a study was launched to investigate a dredge plan suggested by by the electric utility Kemijoki Oy. The project involved mapping the river bed topography to identify the location and extent of hanging dams. A sounding device and ground penetrating radar was used to find the thaw regions in the ice cover. The JJT numerical river ice model was effectively used to study the effect of hanging dams on water levels. However, the ice bridging phenomena was not modelled in a reliable way by the JJT model and will be modelled in the future using the CRISSP2D numerical model. 5 refs., 11 figs.

A Full Scope Nuclear Power Plant Training Simulator: Design and Implementation Experiences

Directory of Open Access Journals (Sweden)

Pedro A. Corcuera

2003-06-01

Full Text Available This paper describes the development of a full scope training simulator for a Spanish nuclear power plant. The simulator is based on a client/server architecture that allows the distributed execution in a network with many users to participate in the same simulation. The interface was designed to support the interaction of the operators with the simulator through virtual panels supported by touch screens with high fidelity graphic displays. The simulation environment is described including the extension added to facilitate an easy operation by instructors. The graphical interface has been developed using component software technology. The appropriate selection of hardware for visualization and interaction, in terms of cost and performance, resulted in a facility much less expensive than the classic hard panels replica simulators and, at the same time, able to fulfill most of the training requirements. The main features of the simulator are the distributed execution control of the models and the flexibility of design and maintenance of the interface. The benefits of virtual panels approach are the automatic switch reposition and tagging, configuration flexibility, low maintenance requirements, or capability to support multiple users distributed across the corporate intranet. After exhaustive validation and testing, the training sessions are being conducted successfully.

A virtual power plant model for time-driven power flow calculations

Directory of Open Access Journals (Sweden)

Gerardo Guerra

2017-11-01

Full Text Available This paper presents the implementation of a custom-made virtual power plant model in OpenDSS. The goal is to develop a model adequate for time-driven power flow calculations in distribution systems. The virtual power plant is modeled as the aggregation of renewable generation and energy storage connected to the distribution system through an inverter. The implemented operation mode allows the virtual power plant to act as a single dispatchable generation unit. The case studies presented in the paper demonstrate that the model behaves according to the specified control algorithm and show how it can be incorporated into the solution scheme of a general parallel genetic algorithm in order to obtain the optimal day-ahead dispatch. Simulation results exhibit a clear benefit from the deployment of a virtual power plant when compared to distributed generation based only on renewable intermittent generation.

Dynamic simulation of a sodium-cooled fast reactor power plant

International Nuclear Information System (INIS)

Shinaishin, M.A.M.

1976-01-01

Simulation of the dynamic behavior of the Clinch River Breeder Reactor Plant (CRBRP) is dealt with. The range of transients under consideration extends from a moderate transient, of the type referred to as Anticipated Transient Without Scram (ATWS), to a transient initiated by an unexpected accident followed by reactor scram. The moderate range of transients can be simulated by a digital simulator referred to as the CRBRP ATWS simulator. Two versions of this simulator were prepared; in one, the plant controllers were not included, whereas, in the other, the controllers were incorporated. In addition to the usual assumption of lumped parameters, uniform heat transfer and point kinetics (prompt jump) have been the main approximations in this and other simulators (see below). Two different transport-delay models have also been installed in all simulators. The simulators were constructed using the DARE-P System, developed by the Electrical Engineering Department at the University of Arizona

Simulation of power plant construction in competitive Korean electricity market

International Nuclear Information System (INIS)

Ahn, Nam Sung; Huh, Sung Chul

2001-01-01

This paper describes the forecast of power plant construction in competitive Korean electricity market. In Korea, KEPCO (Korean Electric Power Corporation, fully controlled by government) was responsible for from the production of the electricity to the sale of electricity to customer. However, the generation part is separated from KEPCO and six generation companies were established for whole sale competition from April 1st, 2001. The generation companies consist of five fossil power companies and one nuclear power company. Fossil power companies are schedule to be sold to private companies including foreign investors. Nuclear power company is owned by government. The competition in generation market will start from 2003. ISO (Independence System Operator) will purchase the electricity from the power exchange market. The market price is determined by the SMP (System Marginal Price) which is decided by the balance between demand and supply of electricity in power exchange market. Under this uncertain circumstance, the energy policy planners are interested to the construction of the power plant in the future. These interests are accelerated due to the recent shortage of electricity supply in California. In the competitive market, investors are no longer interested in the investment for the capital intensive, long lead time generating technologies. Large nuclear and coal plants were no longer the top choices. Instead, investors in the competitive market are interested in smaller, more efficient, cheaper, cleaner technologies such as CCGT (Combined Cycle Gas Turbine). Electricity is treated as commodity in the competitive market. The investor's behavior in the commodity market shows that the new investment decision is made when the market price exceeds the sum of capital cost and variable cost of the new facility and the existing facility utilization depends on the marginal cost of the facility. This investor's behavior can be applied to the new investments for the

Aggregated wind power plant models consisting of IEC wind turbine models

DEFF Research Database (Denmark)

Altin, Müfit; Göksu, Ömer; Hansen, Anca Daniela

2015-01-01

The common practice regarding the modelling of large generation components has been to make use of models representing the performance of the individual components with a required level of accuracy and details. Owing to the rapid increase of wind power plants comprising large number of wind...... turbines, parameters and models to represent each individual wind turbine in detail makes it necessary to develop aggregated wind power plant models considering the simulation time for power system stability studies. In this paper, aggregated wind power plant models consisting of the IEC 61400-27 variable...... speed wind turbine models (type 3 and type 4) with a power plant controller is presented. The performance of the detailed benchmark wind power plant model and the aggregated model are compared by means of simulations for the specified test cases. Consequently, the results are summarized and discussed...

Development of HTGR plant dynamics simulation code

International Nuclear Information System (INIS)

Ohashi, Kazutaka; Tazawa, Yujiro; Mitake, Susumu; Suzuki, Katsuo.

1987-01-01

Plant dynamics simulation analysis plays an important role in the design work of nuclear power plant especially in the plant safety analysis, control system analysis, and transient condition analysis. The authors have developed the plant dynamics simulation code named VESPER, which is applicable to the design work of High Temperature Engineering Test Reactor, and have been improving the code corresponding to the design changes made in the subsequent design works. This paper describes the outline of VESPER code and shows its sample calculation results selected from the recent design work. (author)

Study of nuclear power plant stability. Trip criteria

International Nuclear Information System (INIS)

Beato Castro, D.; Iturbe Uriarte, R.; Wilhelmi Ayza, J.R.

1993-01-01

The influence that nuclear power plants and high voltage power systems have on each other when confronted by disturbances in the offsite network may lead, due to dynamic effects, to plant trip. It is therefore necessary to study the disturbances in the network and the effects on plant equipment by means of dynamic simulations which evaluate the unit protection system and the auxiliary services so as to obtain maximum unit availability without jeopardizing its safety. These studies can be conducted since there are models and software tools capable of simulating dynamic behaviour of the electric system, including the excitation systems and specific speed governors obtainment of valid. (author)

SAPHIR, a simulator for engineering and training on N4-type nuclear power plants

International Nuclear Information System (INIS)

Vovan, C.

1999-01-01

SAPHIR, the new simulator developed by FRAMATOME, has been designed to be a convenient tool for engineering and training for different types of nuclear power plants. Its first application is for the French 'N4' four-loop 1500MWe PWR. The basic features of SAPHIR are: (1) Use of advanced codes for modelling He primary and secondary systems' including an axial steam generator model, (2) Use of a simulation workshop containing different tools for modelling fluid, electrical, instrument and control networks, (3) A Man-Machine Interface designed for an easy and convivial use which can simulate the different computerized control consoles of the 'N4' control room. This paper outlines features and capabilities of this tool, both for engineering and training purposes. (author)

Co-simulation for real time safety verification of nuclear power plants

International Nuclear Information System (INIS)

Boafo, E.K.; Zhang, L.; Nasimi, E.; Gabbar, H.A.

2015-01-01

Small and major accidents and near misses are still occurring in nuclear power plants (NPPs). Risk level has increased with the degradation of NPP equipment and instrumentations. In order to achieve NPP safety, it is important to continuously evaluate risk for all potential hazard and fault propagation scenarios and map protection layers to fault / failure / hazard propagation scenarios to be able to evaluate and verify safety level during NPP operation. There are major limitations in current real time safety verification tools, as it is mainly offline and with no integration to NPP simulation tools. The main goal of this research is to develop real time safety verification with co-simulation tool to be integrated with plant operation support systems. This includes the development of static and dynamic fault semantic network (FSN) to model all possible fault propagation scenarios and the interrelationships among associated process variables. Safety and protection layers along with their reliability are mapped to FSN so that safety levels can be verified during plant operation. Errors between multiphysics models and real time data are modeled to accurately and dynamically tune FSN for each fault propagation scenario. The detailed methodology will show how to integrate process models, construction of static FSN with fault propagation scenarios, and evaluation and tuning of dynamic FSN with probabilistic and process variable interaction values. Principle Component Analysis method is used reduce dimensionality and reduce process variables associated with each fault scenario. Then map independent protection layers (IPL) to FSN with estimated reliability measures of each protection layer to accurately verify safety for different operational scenarios. Intelligent algorithms is used with multivariate techniques to accurate define the interrelation among process variables, in terms of signal strength and time delay, using Genetic Programming (GP), which will provide basis

Simulation program for the dynamic behaviour of the primary system and moderators's circuit of the Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Castano, Jorge; Gvirtzman, H.A.

1981-01-01

A model of digital computation is presented to simulate the primary system of heat transportation, moderator system and the associated systems for adjustment, regulation and control in the PHWR reactor at the Atucha-1 nuclear power plant. The model discusses in a concentrated way the different components and allows the study of the dynamical behaviour of the power plant facing disturbances with respect to a state of stationary regime. General considerations and description of the model are made. The method is described showing flow sheets, graphs and developing basic formulas, simulating a primary system, moderator and secondary system of the steam generator and the main system of regulation. Also an analysis of the results is made, for the case of disturbances which reduce or increase the power of the reactor by 10%. (V.B.) [es

Model-Based Power Plant Master Control

Energy Technology Data Exchange (ETDEWEB)

Boman, Katarina; Thomas, Jean; Funkquist, Jonas

2010-08-15

The main goal of the project has been to evaluate the potential of a coordinated master control for a solid fuel power plant in terms of tracking capability, stability and robustness. The control strategy has been model-based predictive control (MPC) and the plant used in the case study has been the Vattenfall power plant Idbaecken in Nykoeping. A dynamic plant model based on nonlinear physical models was used to imitate the true plant in MATLAB/SIMULINK simulations. The basis for this model was already developed in previous Vattenfall internal projects, along with a simulation model of the existing control implementation with traditional PID controllers. The existing PID control is used as a reference performance, and it has been thoroughly studied and tuned in these previous Vattenfall internal projects. A turbine model was developed with characteristics based on the results of steady-state simulations of the plant using the software EBSILON. Using the derived model as a representative for the actual process, an MPC control strategy was developed using linearization and gain-scheduling. The control signal constraints (rate of change) and constraints on outputs were implemented to comply with plant constraints. After tuning the MPC control parameters, a number of simulation scenarios were performed to compare the MPC strategy with the existing PID control structure. The simulation scenarios also included cases highlighting the robustness properties of the MPC strategy. From the study, the main conclusions are: - The proposed Master MPC controller shows excellent set-point tracking performance even though the plant has strong interactions and non-linearity, and the controls and their rate of change are bounded. - The proposed Master MPC controller is robust, stable in the presence of disturbances and parameter variations. Even though the current study only considered a very small number of the possible disturbances and modelling errors, the considered cases are

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)

Dynamic modeling, simulation and control design of an advanced micro-hydro power plant for distributed generation applications

Energy Technology Data Exchange (ETDEWEB)

Marquez, J.L. [Instituto de Energia Electrica, Universidad Nacional de San Juan, Av. Libertador San Martin Oeste 1109, J5400ARL San Juan (Argentina); Molina, M.G. [CONICET, Instituto de Energia Electrica, Universidad Nacional de San Juan, Av. Libertador San Martin Oeste 1109, J5400ARL San Juan (Argentina); Pacas, J.M. [Institut fuer Leistungselektronik und Elektrische Antriebe, Universitaet Siegen, Fachbereich 12 Hoelderlinstr 3, D 57068 Siegen (Germany)

2010-06-15

A small-scale hydropower station is usually a run-of-river plant that uses a fixed speed drive with mechanical regulation of the turbine water flow rate for controlling the active power generation. This design enables to reach high efficiency over a wide range of water flows but using a complex operating mechanism, which is in consequence expensive and tend to be more affordable for large systems. This paper proposes an advanced structure of a micro-hydro power plant (MHPP) based on a smaller, lighter, more robust and more efficient higher-speed turbine. The suggested design is much simpler and eliminates all mechanical adjustments through a novel electronic power conditioning system for connection to the electric grid. In this way, it allows obtaining higher reliability and lower cost of the power plant. A full detailed model of the MHPP is derived and a new three-level control scheme is designed. The dynamic performance of the proposed MHPP is validated through digital simulations and employing a small-scale experimental set-up. (author)

Digital simulation of a commercial scale high temperature gas-cooled reactor (HTGR) steam power plant

International Nuclear Information System (INIS)

Ray, A.; Bowman, H.F.

1978-01-01

A nonlinear dynamic model of a commercial scale high temperature gas-cooled reactor (HTGR) steam power plant was derived in state-space form from fundamental principles. The plant model is 40th order, time-invariant, deterministic and continuous-time. Numerical results were obtained by digital simulation. Steady-state performance of the nonlinear model was verified with plant heat balance data at 100, 75 and 50 percent load levels. Local stability, controllability and observability were examined in this range using standard linear algorithms. Transfer function matrices for the linearized models were also obtained. Transient response characteristics of 6 system variables for independent step distrubances in 2 different input variables are presented as typical results

Grid Support in Large Scale PV Power Plants using Active Power Reserves

DEFF Research Database (Denmark)

Craciun, Bogdan-Ionut

to validate the performance of the frequency support functions, a flexible grid model with IEEE 12 bus system characteristics has been developed and implemented in RTDS. A power hardware-in-the-loop (PHIL) system composed by 20 kW plant (2 x 10 kW inverters and PV linear simulator) and grid simulator (RTDS......Photovoltaic (PV) systems are in the 3rd place in the renewable energy market, after hydro and wind power. The increased penetration of PV within the electrical power system has led to stability issues of the entire grid in terms of its reliability, availability and security of the supply....... As a consequence, Large scale PV Power Plants (LPVPPs) operating in Maximum Power Point (MPP) are not supporting the electrical network, since several grid triggering events or the increased number of downward regulation procedures have forced European Network of Transmission System Operators for Electricity...

Quantitative assessment of aquatic impacts of power plants

Energy Technology Data Exchange (ETDEWEB)

McKenzie, D.H.; Arnold, E.M.; Skalski, J.R.; Fickeisen, D.H.; Baker, K.S.

1979-08-01

Progress is reported in a continuing study of the design and analysis of aquatic environmental monitoring programs for assessing the impacts of nuclear power plants. Analysis of data from Calvert Cliffs, Pilgrim, and San Onofre nuclear power plants confirmed the generic applicability of the control-treatment pairing design suggested by McKenzie et al. (1977). Substantial progress was made on the simulation model evaluation task. A process notebook was compiled in which each model equation was translated into a standardized notation. Individual model testing and evaluating was started. The Aquatic Generalized Environmental Impact Simulator (AGEIS) was developed and will be tested using data from Lake Keowee, South Carolina. Further work is required to test the various models and perfect AGEIS for impact analyses at actual power plant sites. Efforts on the hydrologic modeling task resulted in a compendium of models commonly applied to nuclear power plants and the application of two well-received hydrodynamic models to data from the Surry Nuclear Power Plant in Virginia. Conclusions from the study of these models indicate that slight inaccuracies of boundary data have little influence on mass conservation and accurate bathymetry data are necessary for conservation of mass through the model calculations. The hydrologic modeling task provides valuable reference information for model users and monitoring program designers.

Quantitative assessment of aquatic impacts of power plants

International Nuclear Information System (INIS)

McKenzie, D.H.; Arnold, E.M.; Skalski, J.R.; Fickeisen, D.H.; Baker, K.S.

1979-08-01

Progress is reported in a continuing study of the design and analysis of aquatic environmental monitoring programs for assessing the impacts of nuclear power plants. Analysis of data from Calvert Cliffs, Pilgrim, and San Onofre nuclear power plants confirmed the generic applicability of the control-treatment pairing design suggested by McKenzie et al. (1977). Substantial progress was made on the simulation model evaluation task. A process notebook was compiled in which each model equation was translated into a standardized notation. Individual model testing and evaluating was started. The Aquatic Generalized Environmental Impact Simulator (AGEIS) was developed and will be tested using data from Lake Keowee, South Carolina. Further work is required to test the various models and perfect AGEIS for impact analyses at actual power plant sites. Efforts on the hydrologic modeling task resulted in a compendium of models commonly applied to nuclear power plants and the application of two well-received hydrodynamic models to data from the Surry Nuclear Power Plant in Virginia. Conclusions from the study of these models indicate that slight inaccuracies of boundary data have little influence on mass conservation and accurate bathymetry data are necessary for conservation of mass through the model calculations. The hydrologic modeling task provides valuable reference information for model users and monitoring program designers

Review of Methods Related to Assessing Human Performance in Nuclear Power Plant Control Room Simulations

Energy Technology Data Exchange (ETDEWEB)

Katya L Le Blanc; Ronald L Boring; David I Gertman

2001-11-01

With the increased use of digital systems in Nuclear Power Plant (NPP) control rooms comes a need to thoroughly understand the human performance issues associated with digital systems. A common way to evaluate human performance is to test operators and crews in NPP control room simulators. However, it is often challenging to characterize human performance in meaningful ways when measuring performance in NPP control room simulations. A review of the literature in NPP simulator studies reveals a variety of ways to measure human performance in NPP control room simulations including direct observation, automated computer logging, recordings from physiological equipment, self-report techniques, protocol analysis and structured debriefs, and application of model-based evaluation. These methods and the particular measures used are summarized and evaluated.

Simulation model for man-machine systems in nuclear power plants. Vol. 4

Energy Technology Data Exchange (ETDEWEB)

Falk, A

1981-01-01

At first, volume 4 was to describe the EDP-bound simulation model in the final programme version. This problem was tackled as a development project, however, it could not be solved because of the difficult time schedule and the commissioning of the new computing centre at the Fachhochschule Flensburg. The assignment described in volume 3, chapter 2, already contains the optimization stages planned for 1981 but still uses a special programming language 'Prozess-FORTRAN' for older digital computers. That is why the development of a new version of the programming system in Standard-FORTRAN should be postponed. It should also include a more comprehensive practical data bank for nuclear power plants. The present short report as well as the following more comprehensive final report lay more emphasis on the presentation of a functional range of application of the simulation model.

Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.

1992-01-01

This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Third Annual Technical Progress report summarizes the period from September 1991 to October 1992. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. His philosophy, is to improve public perception of the safety of nuclear power plants by incorporating a high degree of automation where a greatly simplified operator control console minimizes the possibility of human error in power plant operations. To achieve this goal, a hierarchically distributed control system with automated responses to plant upset conditions was pursued in this research. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 stem plant. Emphasized in this Third Annual Technical Progress Report is the continuing development of the in-plant intelligent control demonstration for the final project milestone and includes: simulation validation and the initial approach to experiment formulation

Effect of increased renewables generation on operation of thermal power plants

International Nuclear Information System (INIS)

Eser, Patrick; Singh, Antriksh; Chokani, Ndaona; Abhari, Reza S.

2016-01-01

Highlights: • Impacts of increased renewables in central European transmission system are assessed. • Individual transmission lines and power plants of transmission system are modelled. • Starts and ramps of thermal power plants significantly increase with increased renewables. • Impact of renewables on thermal power plants is highly dependent on location. - Abstract: High spatial and temporal resolution optimal power flow simulations of the 2013 and 2020 interconnected grid in Central Western and Eastern Europe regions are undertaken to assess the impact of an increased penetration of renewables on thermal power plants. In contrast to prior studies, the present work models each individual transmission line and power plant within the two regions. Furthermore, for conventional plants, electricity costs are determined with respect to fuel type, nameplate capacity, operating condition and geographic location; cycling costs are modeled as function of the recent operational history. For renewable power plants, costs and available power are determined using mesoscale weather simulations and hydrology models. Countrywide validation of the simulations shows that all renewable and most conventional power production is predicted with less than 10% error. It is shown that the increased penetration of renewables in 2020 will induce a 4–23% increase in the number of starts of conventional plants. The number of load ramps significantly increases by 63–181%, which underlines the necessity for equipment manufacturers and utilities to adapt to scenarios of high penetration of renewables. The increased cycling operation of coal plants is shown to depend strongly on the power plant’s location and is mainly observed in Germany and the Czech Republic. Austrian coal plants are cycled less because they supply more base load power to southern Germany, where several nuclear power plants will be phased out by 2020. Thus there is a need for more transmission capacity along

Natural interfaces for interacting with a virtual control desk of a nuclear power plant simulator

International Nuclear Information System (INIS)

Aghina, Mauricio Alves da Cunha e

2012-01-01

Due to very strict standards of safe operation of a nuclear power plant operators must be well trained so they can operate it within the necessary safety procedures. This is done through training simulators, which enable the user operation, as close as possible to the real control desk, and can be inserted accident situations, so they train, how to return the plant to a normal operating condition. Normally is used two types of simulator. Preferred is the full scope simulator, what is a computational dynamics program of the plant used in conjunction with a physical replica of the control desk, but this type of simulator involves a high construction cost. The second type is what uses synoptic windows of various regions of the original control desk, its construction cost is smaller, but it have a little fidelity to the original appearance of the table. Currently, with the use of virtual reality, control desks can be modeled in 3D, making the simulator interface is very similar to the appearance of the real control desk with a low cost construction. This work shows the use of natural interfaces for operator interaction with the virtual control desk, in order that it does not use any mechanical device for displaying and acting with it. For procedures that were used, such as: computer vision to recognize the position of the operator's and observation of their hands to the work of the desk controls and voice recognition. (author)

Application perspectives of simulation techniques CFD in nuclear power plants; Perspectivas de aplicacion de tecnicas de modelado CFD en plantas nucleoelectricas

Energy Technology Data Exchange (ETDEWEB)

Galindo G, I. F., E-mail: igalindo@iie.org.mx [Instituto de Investigaciones Electricas, Reforma No. 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico)

2013-10-15

The scenarios simulation in nuclear power plants is usually carried out with system codes that are based on concentrated parameters networks. However situations exist in some components where the flow is predominantly 3-D, as they are the natural circulation, mixed and stratification phenomena. The simulation techniques of computational fluid dynamics (CFD) have the potential to simulate these flows numerically. The use of CFD simulations embraces many branches of the engineering and continues growing, however, in relation to its application with respect to the problems related with the safety in nuclear power plants, has a smaller development, although is accelerating quickly and is expected that in the future they play a more emphasized paper in the analyses. A main obstacle to be able to achieve a general acceptance of the CFD is that the simulations should have very complete validation studies, sometimes not available. In this article a general panorama of the state of the methods application CFD in nuclear power plants is presented and the problem associated to its routine application and acceptance, including the view point of the regulatory authorities. Application examples are revised in those that the CFD offers real benefits and are also presented two illustrative study cases of the application of CFD techniques. The case of a water recipient with a heat source in its interior, similar to spent fuel pool of a nuclear power plant is presented firstly; and later the case of the Boron dilution of a water volume that enters to a nuclear reactor is presented. We can conclude that the CFD technology represents a very important opportunity to improve the phenomena understanding with a strong component 3-D and to contribute in the uncertainty reduction. (Author)

Study on the Simulation of Crud Formation using Piping Materials of Nuclear Power Plant in High Temperature Water

International Nuclear Information System (INIS)

Kim, Sang Hyun; Kim, In Sup; Lee, Kun Jai

2005-01-01

High temperature - high pressure apparatus was developed to simulate nickel fewite corrosion products which were main compositions of the radioactive crud in the nuclear power plant. Corrosion product similar to the crud was obtained by a tube accumulator system. Nickel alloy (Inconel 690) and carbon steel (SA106 Gr. C) were corroded at 270 in the corrosion product generator. Ni ions and Fe ions dissolved by corrosion reaction were able to be transported to the accumulator because the crud generation mechanism was the solubility change with temperature. To evaluate the properties of simulated corrosion products, scanning electron microscope (SEM) observation and EDAX analysis were performed. SEM observation of corrosion product showed the needle like or crystal structure of oxide depending on precipitating location. The crystal oxide was the nickel ferrite, which was similar to the crud in nuclear power plants.

Nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

Requirements to be made on the methodology of staff training on a nuclear power plant simulator of the new Konvoi generation

International Nuclear Information System (INIS)

Reinartz, S.J.; Reinartz, G.

1984-01-01

This report is based on a review of the literature published on simulator training and on discussions with representatives from the German nuclear power plant operator training schools. A brief description of the organisation and content of the simulator training of control room operators in a number of countries, together with a catagorisation of the various types of simulators which are used. The concepts of the systems approach to training and simulator fidelity are discussed. Some general training principles which are considered important for simulator training are summarised. From the available descriptions and analyses of control room operator tasks, the skills (in most general terms) which can be trained at simulators have been identified. Methods for training these skills which are used in the simulator training programmes in various industries and which have been developed in research work in the area of training psychology have been summarised. Using these methods as a basis, the necessary instructor facilities which should be included in the design of a full simulator for the Konvoi generation of nuclear power plants have been derived. (orig.) [de

Criteria for safety-related nuclear-power-plant operator actions: 1982 pressurized-water-reactor (PWR) simulator exercises

International Nuclear Information System (INIS)

Crowe, D.S.; Beare, A.N.; Kozinsky, E.J.; Haas, P.M.

1983-06-01

The primary objective of the Safety-Related Operator Action (SROA) Program at Oak Ridge National Laboratory is to provide a data base to support development of criteria for safety-related actions by nuclear power plant operators. When compared to field data collected on similar events, a base of operator performance data developed from the simulator experiments can then be used to establish safety-related operator action design evaluation criteria, evaluate the effects of performance shaping factors, and support safety/risk assessment analyses. This report presents data obtained from refresher training exercises conducted in a pressurized water reactor (PWR) power plant control room simulator. The 14 exercises were performed by 24 teams of licensed operators from one utility, and operator performance was recorded by an automatic Performance Measurement System. Data tapes were analyzed to extract operator response times (RTs) and error rate information. Demographic and subjective data were collected by means of brief questionnaires and analyzed in an attempt to evaluate the effects of selected performance shaping factors on operator performance

FleetPower: Creating Virtual Power Plants in Sustainable Smart Electricity Markets

NARCIS (Netherlands)

M.T. Kahlen (Micha); W. Ketter (Wolfgang); A. Gupta (Alok)

2017-01-01

textabstractElectric vehicles have the potential to be used as virtual power plants to provide reliable back-up power. This generates additional profits for carsharing rental firms, who rent vehicles by the minute. We show this by developing a discrete event simulation platform based on real-time

LNG plant combined with power plant

Energy Technology Data Exchange (ETDEWEB)

Aoki, I; Kikkawa, Y [Chiyoda Chemical Engineering and Construction Co. Ltd., Tokyo (Japan)

1997-06-01

The LNG plant consumers a lot of power of natural gas cooling and liquefaction. In some LNG plant location, a rapid growth of electric power demand is expected due to the modernization of area and/or the country. The electric power demand will have a peak in day time and low consumption in night time, while the power demand of the LNG plant is almost constant due to its nature. Combining the LNG plant with power plant will contribute an improvement the thermal efficiency of the power plant by keeping higher average load of the power plant, which will lead to a reduction of electrical power generation cost. The sweet fuel gas to the power plant can be extracted from the LNG plant, which will be favorable from view point of clean air of the area. (Author). 5 figs.

LNG plant combined with power plant

International Nuclear Information System (INIS)

Aoki, I.; Kikkawa, Y.

1997-01-01

The LNG plant consumers a lot of power of natural gas cooling and liquefaction. In some LNG plant location, a rapid growth of electric power demand is expected due to the modernization of area and/or the country. The electric power demand will have a peak in day time and low consumption in night time, while the power demand of the LNG plant is almost constant due to its nature. Combining the LNG plant with power plant will contribute an improvement the thermal efficiency of the power plant by keeping higher average load of the power plant, which will lead to a reduction of electrical power generation cost. The sweet fuel gas to the power plant can be extracted from the LNG plant, which will be favorable from view point of clean air of the area. (Author). 5 figs

Wind Turbine and Wind Power Plant Modelling Aspects for Power System Stability Studies

DEFF Research Database (Denmark)

Altin, Müfit; Hansen, Anca Daniela; Göksu, Ömer

2014-01-01

Large amount of wind power installations introduce modeling challenges for power system operators at both the planning and operational stages of power systems. Depending on the scope of the study, the modeling details of the wind turbine or the wind power plant are required to be different. A wind...... turbine model which is developed for the short-term voltage stability studies can be inaccurate and sufficient for the frequency stability studies. Accordingly, a complete and detailed wind power plant model for every kind of study is not feasible in terms of the computational time and also...... and wind power plants are reviewed for power system stability studies. Important remarks of the models are presented by means of simulations to emphasize the impact of these modelling details on the power system....

Real-time simulation of MHD/steam power plants by digital parallel processors

International Nuclear Information System (INIS)

Johnson, R.M.; Rudberg, D.A.

1981-01-01

Attention is given to a large FORTRAN coded program which simulates the dynamic response of the MHD/steam plant on either a SEL 32/55 or VAX 11/780 computer. The code realizes a detailed first-principle model of the plant. Quite recently, in addition to the VAX 11/780, an AD-10 has been installed for usage as a real-time simulation facility. The parallel processor AD-10 is capable of simulating the MHD/steam plant at several times real-time rates. This is desirable in order to develop rapidly a large data base of varied plant operating conditions. The combined-cycle MHD/steam plant model is discussed, taking into account a number of disadvantages. The disadvantages can be overcome with the aid of an array processor used as an adjunct to the unit processor. The conversion of some computations for real-time simulation is considered

LWR [Light Water Reactor] power plant simulations using the AD10 and AD100 systems

International Nuclear Information System (INIS)

Wulff, W.; Cheng, H.S.; Chien, C.J.; Jang, J.Y.; Lin, H.C.; Mallen, A.N.; Wang, S.J.

1989-01-01

Boiling (BWR) and Pressurized (PWR) Water Reactor Power Plants are being simulated at BNL with the AD10 and AD100 Peripheral Processor Systems. The AD10 system has been used for BWR simulations since 1984 for safety analyses, emergency training and optimization studies. BWR simulation capabilities have been implemented recently on the AD100 system and PWR simulation capabilities are currently being developed under the auspices of international cooperation. Modeling and simulation methods are presented with emphasis on the simulation of the Nuclear Steam Supply System. Results are presented for BWR simulation and performance characteristics are compared of the AD10 and AD100 systems. It will be shown that the AD100 simulates two times faster than two AD10 processors operating in parallel and that the computing capacity of one AD100 (with FMU processor) is twice as large as that of two AD10 processors. 9 refs., 5 figs., 1 tab

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

Plant analyzer development for high-speed interactive simulation of BWR plant transients

International Nuclear Information System (INIS)

Wulff, W.; Cheng, H.S.; Mallen, A.N.

1986-01-01

Advanced modeling techniques have been combined with modern, special-purpose peripheral minicomputer technology to develop a plant analyzer which provides realistic and accurate predictions of plant transients and severe off-normal events in nuclear power plants through on-line simulations at speeds of approximately 10 times faster than actual process speeds. The new simulation technology serves not only for carrying out routinely and efficiently safety analyses, optimizations of emergency procedures and design changes, parametric studies for obtaining safety margins and for generic training but also for assisting plant operations. Five modeling principles are presented which serve to achieve high-speed simulation of neutron kinetics, thermal conduction, nonhomogeneous and nonequilibrium two-phase flow coolant dynamics, steam line acoustical effects, and the dynamics of the balance of plant and containment systems, control systems and plant protection systems. 21 refs

Design of compact nuclear power marine engineering simulator

International Nuclear Information System (INIS)

Gao Jinghui; Xing Hongchuan; Zhang Ronghua; Yang Yanhua; Xu Jijun

2004-01-01

The essentiality of compact nuclear power marine engineering simulator (NPMES) is discussed. The technology of nuclear power plant engineering simulator (NPPES) for NPMES development is introduced, and the function design, general design and model design are given in details. A compact NPMES based on the nuclear power marine of 'Mutsu' is developed. The design can help the development of NPMES, which will improve operation safety and management efficiency of marine. (authors)

Nuclear power plant status diagnostics using artificial neural networks

International Nuclear Information System (INIS)

Bartlett, E.B.; Uhrig, R.E.

1991-01-01

In this work, the nuclear power plant operating status recognition issue is investigated using artificial neural networks (ANNs). The objective is to train an ANN to classify nuclear power plant accident conditions and to assess the potential of future work in the area of plant diagnostics with ANNS. To this end, an ANN was trained to recognize normal operating conditions as well as potentially unsafe conditions based on nuclear power plant training simulator generated accident scenarios. These scenarios include; hot and cold leg loss of coolant, control rod ejection, loss of offsite power, main steam line break, main feedwater line break and steam generator tube leak accidents. Findings show that ANNs can be used to diagnose and classify nuclear power plant conditions with good results

The ability to use FLEXPART in simulation of the long-range radioactive materials dispersed from nuclear power plants near Vietnam border

International Nuclear Information System (INIS)

Pham Kim Long; Pham Duy Hien; Nguyen Hao Quang; Do Xuan Anh; Duong Duc Thang; Doan Quang Tuyen

2016-01-01

FLEXPART is a Lagrangian transport and dispersion model suitable for the simulation of a large range of atmospheric transport processes. FLEXPART has been researched and applied in simulation of the long-range dispersion of radioactive materials. It can be applicable to the problem of radioactive materials released from the nuclear power plants impact on Vietnam. This report presents simulation of radioactive dispersion from the accident assumed Fangchenggang and Changjiang nuclear power plants in China with the FLEXPART, using meteorological data from the National Centers for Environmental Prediction (NCEP). The results of simulations and analyzing showed good applicability of FLEXPART for a long-range radioactive materials dispersion. The preliminary simulation results show that the impact of the radioactive material dispersion in Vietnam varies by the well-known characteristics of the monsoon of our country. Winter is the time when the dominant northeast winds up radioactive dispersion most towards our country, its sphere of influence extends from the Northeast (Quang Ninh) to North Central (Da Nang). (author)

Simulation of steam-water and binary geothermal power plants

International Nuclear Information System (INIS)

Popel', O.S.; Frid, S.E.; Shpil'rajn, Eh.Eh.

2004-01-01

The generalized scheme of the geothermal power plant (GeoPP), assuming the possibility of the electric power production in the steam-water turbine or in the turbine on the low-boiling working body, is considered. The GeoPP mathematical model, making it possible to carry out the comparison of the power indices of various GeoPP schemes and analysis of the calculational indices sensitivity of these schemes to the mode parameters change, is presented [ru

Manpower simulation for the power plant design engineering

International Nuclear Information System (INIS)

Moon, B.S.; Juhn, P.E.

1982-01-01

Some observation from the examination of actual manhour curves for the power design engineering obtained from Sargent and Lundy Engineers and of a few of the model curves proposed by Bechtel, are analyzed in this paper. A model curve representing typical design engineering manhour has been determined as probability density function for the Gamma Distribution. By means of this model curve, we strategically forecast the future engineering manpower requirements to meet the Covernment's long range nuclear power plan. As a sensitivity analysis, the directions for the localization of nuclear power plant design engineering, are studied in terms of the performance factor for the experienced versus inexperienced engineers. (Author)

Abnormal transient analysis by using PWR plant simulator, (2)

International Nuclear Information System (INIS)

Naitoh, Akira; Murakami, Yoshimitsu; Yokobayashi, Masao.

1983-06-01

This report describes results of abnormal transient analysis by using a PWR plant simulator. The simulator is based on an existing 822MWe power plant with 3 loops, and designed to cover wide range of plant operation from cold shutdown to full power at EOL. In the simulator, malfunctions are provided for abnormal conditions of equipment failures, and in this report, 17 malfunctions for secondary system and 4 malfunctions for nuclear instrumentation systems were simulated. The abnormal conditions are turbine and generator trip, failure of condenser, feedwater system and valve and detector failures of pressure and water level. Fathermore, failure of nuclear instrumentations are involved such as source range channel, intermediate range channel and audio counter. Transient behaviors caused by added malfunctions were reasonable and detail information of dynamic characteristics for turbine-condenser system were obtained. (author)

Exergetic analysis of cogeneration plants through integration of internal combustion engine and process simulators

Energy Technology Data Exchange (ETDEWEB)

Carvalho, Leonardo de Oliveira [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)], E-mail: leonardo.carvalho@petrobras.com.br; Leiroz, Albino Kalab; Cruz, Manuel Ernani [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Mecanica], Emails: leiroz@mecanica.ufrj.br, manuel@mecanica.ufrj.br

2010-07-01

Internal combustion engines (ICEs) have been used in industry and power generation much before they were massively employed for transportation. Their high reliability, excellent power-to-weight ratio, and thermal efficiency have made them a competitive choice as main energy converters in small to medium sized power plants. Process simulators can model ICE powered energy plants with limited depth, due to the highly simplified ICE models used. Usually a better understanding of the global effects of different engine parameters is desirable, since the combustion process within the ICE is typically the main cause of exergy destruction in systems which utilize them. Dedicated commercial ICE simulators have reached such a degree of maturity, that they can adequately model a wide spectrum of phenomena that occur in ICEs. However, ICE simulators are unable to incorporate the remaining of power plant equipment and processes in their models. This paper presents and exploits the integration of an internal combustion engine simulator with a process simulator, so as to evaluate the construction of a fully coupled simulation platform to analyze the performance of ICE-based power plants. A simulation model of an actual cogeneration plant is used as a vehicle for application of the proposed computational methodology. The results show that by manipulating the engine mapping parameters, the overall efficiency of the plant can be improved. (author)

Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

International Nuclear Information System (INIS)

Hou, Xue Yan; Li, Shu; Li, Qing

2011-01-01

Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier

Simulation of the dynamic behaviour of the secondary circuit of a WWER-440 type nuclear power plant Pt. 2

International Nuclear Information System (INIS)

Doorenbos, J.; Gacs, A.; Kiss, Zs.

1987-12-01

This report describes the dynamic simulation models of the most important controllers of the secondary circuit of a WWER-440 type nuclear power plant, i.e., the hydraulic turbine controller and the level controls of the condenser hotwell and that of the feedwater tank. Simulation results are also presented. (For dynamic simulation models of the primary circuit of WWER-440 type reactors see Reports KFKI--1983-127 and KFKI--1985-08.) (author) 15 figs

Validation of SIMULATE-3K for stability analysis of Laguna Verde nuclear plant

Energy Technology Data Exchange (ETDEWEB)

Castillo, Rogelio, E-mail: rogelio.castillo@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Alonso, Gustavo, E-mail: gustavo.alonso@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Instituto Politecnico Nacional, Unidad Profesional Adolfo Lopez Mateos, Ed. 9, Lindavista, D.F. 07300 (Mexico); Ramírez, J. Ramón, E-mail: ramon.ramirez@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico)

2013-12-15

Highlights: • Neutronic/thermal hydraulic event in Laguna Verde is modeled. • A good agreement is obtained between SIMULATE-3K results and data plant for frequency and DR. • Other noise analysis techniques are used for the same purpose with good agreement. • Validation of SIMULATE-3K for stability analysis of Laguna Verde is confirmed - Abstract: Boiling Water Reactors are two phase flow systems which are susceptible to different types of flow instabilities. Among these are the coupled neutronic/thermal-hydraulic instabilities, these may compromise established fuel safety limits. These instabilities are characterized by periodic core-power and hydraulic oscillations. SIMULATE-3K code has been tested for stability analysis for several benchmarks, however to qualify the SIMULATE-3K code for a particular power plant a specific reactor plant analysis must be done. In this paper, the plant model of Laguna Verde Nuclear Power Plant is built and SIMULATE-3K is tested against the 1995 coupled neutronic/thermal-hydraulic instability event of Laguna Verde. Results obtained show the adequacy of this code to specific Laguna Verde power plant stability analysis.

Minimum load reduction for once-through boiler power plants

International Nuclear Information System (INIS)

Colombo, P.; Godina, G.; Manganelli, R.

2001-01-01

In Italy the liberalization process of energy market is giving particular importance to the optimization of power plants performances; especially for those that will be called to satisfy grid peak demands. On those plants some techniques have been experimented for the reduction of minimum load; these techniques, investigated and tested by an engineering dynamic simulator, have been sequentially tested on plant. The minimum load for up 320 MW of Tavazzano power plants has been diminished from 140 down to 80 MW without plant modification [it

Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.

1993-01-01

This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 steam plant. Described in this Final (Third Annual) Technical Progress Report is the accomplishment of the project's final milestone, an in-plant intelligent control experiment conducted on April 1, 1993. The development of the experiment included: simulation validation, experiment formulation and final programming, procedure development and approval, and experimental results. Other third year developments summarized in this report are: (1) a theoretical foundation for Reconfigurable Hybrid Supervisory Control, (2) a steam plant diagnostic system, (3) control console design tools and (4) other advanced and intelligent control

Development of Simulation-Based Evaluation System for Iterative Design of Human-Machine Interface in a Nuclear Power Plant - Application for Reducing Workload

International Nuclear Information System (INIS)

Fumizawa, Motoo; Kameda, Akiyuki; Nakagawa, Takashi; Wu Wei; Yoshikawa, Hidekazu

2003-01-01

Development of simulation-based evaluation and analysis support system for man-machine interface design (SEAMAID) has been conducted in the Nuclear Power Engineering Corporation to simulate the behavior of a few operators and the human-machine interface (HMI) in a commercialized pressurized water reactor plant. The workload is one of the key factors with respect to reducing the human error in the operation of nuclear power plants. In order to produce a high-quality design of HMI, the evaluation method was developed to simulate and analyze the operator's workload. Our method was adopted from the cognition model proposed by Reason. The workload such as the length of the visual point movement and the moving length of the operators was visualized in a monitor image during the simulation, and then recorded as a movie-file. As a consequence, the validation of SEAMAID was clarified

Theory model and experiment research about the cognition reliability of nuclear power plant operators

International Nuclear Information System (INIS)

Fang Xiang; Zhao Bingquan

2000-01-01

In order to improve the reliability of NPP operation, the simulation research on the reliability of nuclear power plant operators is needed. Making use of simulator of nuclear power plant as research platform, and taking the present international reliability research model-human cognition reliability for reference, the part of the model is modified according to the actual status of Chinese nuclear power plant operators and the research model of Chinese nuclear power plant operators obtained based on two-parameter Weibull distribution. Experiments about the reliability of nuclear power plant operators are carried out using the two-parameter Weibull distribution research model. Compared with those in the world, the same results are achieved. The research would be beneficial to the operation safety of nuclear power plant

Reliability research to nuclear power plant operators based on several methods

International Nuclear Information System (INIS)

Fang Xiang; Li Fu; Zhao Bingquan

2009-01-01

The paper utilizes many kinds of international reliability research methods, and summarizes the review of reliability research of Chinese nuclear power plant operators in past over ten years based on the simulator platform of nuclear power plant. The paper shows the necessity and feasibility of the research to nuclear power plant operators from many angles including human cognition reliability, fuzzy mathematics model and psychological research model, etc. It will be good to the safe operation of nuclear power plant based on many kinds of research methods to the reliability research of nuclear power plant operators. (authors)

Protection Performance Simulation of Coal Tar-Coated Pipes Buried in a Domestic Nuclear Power Plant Using Cathodic Protection and FEM Method

Energy Technology Data Exchange (ETDEWEB)

Chang, H. Y.; Lim, B. T.; Kim, K. S.; Kim, J. W.; Park, H. B. [KEPCO Engineering and Construction Company, Gimcheon (Korea, Republic of); Kim, Y. S.; Kim, K. T. [Andong National University, Andong (Korea, Republic of)

2017-06-15

Coal tar-coated pipes buried in a domestic nuclear power plant have operated under the cathodic protection. This work conducted the simulation of the coating performance of these pipes using a FEM method. The pipes, being ductile cast iron have been suffered under considerably high cathodic protection condition beyond the appropriate condition. However, cathodic potential measured at the site revealed non-protected status. Converting from 3D CAD data of the power plant to appropriate type for a FEM simulation was conducted and cathodic potential under the applied voltage and current was calculated using primary and secondary current distribution and physical conditions. FEM simulation for coal tar-coated pipe without defects revealed over-protection condition if the pipes were well-coated. However, the simulation for coal tar-coated pipes with many defects predict that the coated pipes may be severely degraded. Therefore, for high risk pipes, direct examination and repair or renewal of pipes are strongly recommended.

Measuring Human Performance in Simulated Nuclear Power Plant Control Rooms Using Eye Tracking

Energy Technology Data Exchange (ETDEWEB)

Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bower, Gordon Ross [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary Alexander [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hill, Rachael Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States); LeBlanc, Katya Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-11-01

Control room modernization will be an important part of life extension for the existing light water reactor fleet. As part of modernization efforts, personnel will need to gain a full understanding of how control room technologies affect performance of human operators. Recent advances in technology enables the use of eye tracking technology to continuously measure an operator’s eye movement, which correlates with a variety of human performance constructs such as situation awareness and workload. This report describes eye tracking metrics in the context of how they will be used in nuclear power plant control room simulator studies.

Measuring Human Performance in Simulated Nuclear Power Plant Control Rooms Using Eye Tracking

International Nuclear Information System (INIS)

Kovesdi, Casey Robert; Rice, Brandon Charles; Bower, Gordon Ross; Spielman, Zachary Alexander; Hill, Rachael Ann; LeBlanc, Katya Lee

2015-01-01

Control room modernization will be an important part of life extension for the existing light water reactor fleet. As part of modernization efforts, personnel will need to gain a full understanding of how control room technologies affect performance of human operators. Recent advances in technology enables the use of eye tracking technology to continuously measure an operator's eye movement, which correlates with a variety of human performance constructs such as situation awareness and workload. This report describes eye tracking metrics in the context of how they will be used in nuclear power plant control room simulator studies.

Are atomic power plants saver than nuclear power plants

International Nuclear Information System (INIS)

Roeglin, H.C.

1977-01-01

It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.) [de

Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

Energy Technology Data Exchange (ETDEWEB)

Hou, Xue Yan; Li, Shu; Li, Qing [China Nuclear Power Operation Technology Co., Wuhan (China)

2011-08-15

Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier.

Validation of CALMET/CALPUFF models simulations around a large power plant stack

Energy Technology Data Exchange (ETDEWEB)

Hernandez-Garces, A.; Souto, J. A.; Rodriguez, A.; Saavedra, S.; Casares, J. J.

2015-07-01

Calmest/CALPUFF modeling system is frequently used in the study of atmospheric processes and pollution, and several validation tests were performed until now; nevertheless, most of them were based on experiments with a large compilation of surface and aloft meteorological measurements, rarely available. At the same time, the use of a large operational smokestack as tracer/pollutant source is not usual. In this work, first CALMET meteorological diagnostic model is nested to WRF meteorological prognostic model simulations (3x3 km{sup 2} horizontal resolution) over a complex terrain and coastal domain at NW Spain, covering 100x100 km{sup 2}, with a coal-fired power plant emitting SO{sub 2}. Simulations were performed during three different periods when SO{sub 2} hourly glc peaks were observed. NCEP reanalysis were applied as initial and boundary conditions. Yong Sei University-Pleim-Chang (YSU) PBL scheme was selected in the WRF model to provide the best input to three different CALMET horizontal resolutions, 1x1 km{sup 2}, 0.5x0.5 km{sup 2}, and 0.2x0.2 km{sup 2}. The best results, very similar between them, were achieved using the last two resolutions; therefore, the 0.5x0.5 km{sup 2} resolution was selected to test different CALMET meteorological inputs, using several combinations of WRF outputs and/or surface and upper-air measurements available in the simulation domain. With respect to meteorological aloft models output, CALMET PBL depth estimations are very similar to PBL depth estimations using upper-air measurements (rawinsondes), and significantly better than WRF PBL depth results. Regarding surface models surface output, the available meteorological sites were divided in two groups, one to provide meteorological input to CALMET (when applied), and another to models validation. Comparing WRF and CALMET outputs against surface measurements (from sites for models validation) the lowest RMSE was achieved using as CALMET input dataset WRF output combined with

Validation of CALMET/CALPUFF models simulations around a large power plant stack

Energy Technology Data Exchange (ETDEWEB)

Hernandez-Garces, A.; Souto Rodriguez, J.A.; Saavedra, S.; Casares, J.J.

2015-07-01

CALMET/CALPUFF modeling system is frequently used in the study of atmospheric processes and pollution, and several validation tests were performed until now; nevertheless, most of them were based on experiments with a large compilation of surface and aloft meteorological measurements, rarely available. At the same time, the use of a large operational smokestack as tracer/pollutant source is not usual. In this work, first CALMET meteorological diagnostic model is nested to WRF meteorological prognostic model simulations (3x3 km2 horizontal resolution) over a complex terrain and coastal domain at NW Spain, covering 100x100 km2 , with a coal-fired power plant emitting SO2. Simulations were performed during three different periods when SO2 hourly glc peaks were observed. NCEP reanalysis were applied as initial and boundary conditions. Yong Sei University-Pleim-Chang (YSU) PBL scheme was selected in the WRF model to provide the best input to three different CALMET horizontal resolutions, 1x1 km2 , 0.5x0.5 km2 , and 0.2x0.2 km2. The best results, very similar between them, were achieved using the last two resolutions; therefore, the 0.5x0.5 km2 resolution was selected to test different CALMET meteorological inputs, using several combinations of WRF outputs and/or surface and upper-air measurements available in the simulation domain. With respect to meteorological aloft models output, CALMET PBL depth estimations are very similar to PBL depth estimations using upper-air measurements (rawinsondes), and significantly better than WRF PBL depth results. Regarding surface models surface output, the available meteorological sites were divided in two groups, one to provide meteorological input to CALMET (when applied), and another to models validation. Comparing WRF and CALMET outputs against surface measurements (from sites for models validation) the lowest RMSE was achieved using as CALMET input dataset WRF output combined with surface measurements (from sites for CALMET model

Validation of CALMET/CALPUFF models simulations around a large power plant stack

International Nuclear Information System (INIS)

Hernandez-Garces, A.; Souto, J. A.; Rodriguez, A.; Saavedra, S.; Casares, J. J.

2015-01-01

Calmest/CALPUFF modeling system is frequently used in the study of atmospheric processes and pollution, and several validation tests were performed until now; nevertheless, most of them were based on experiments with a large compilation of surface and aloft meteorological measurements, rarely available. At the same time, the use of a large operational smokestack as tracer/pollutant source is not usual. In this work, first CALMET meteorological diagnostic model is nested to WRF meteorological prognostic model simulations (3x3 km 2 horizontal resolution) over a complex terrain and coastal domain at NW Spain, covering 100x100 km 2 , with a coal-fired power plant emitting SO 2 . Simulations were performed during three different periods when SO 2 hourly glc peaks were observed. NCEP reanalysis were applied as initial and boundary conditions. Yong Sei University-Pleim-Chang (YSU) PBL scheme was selected in the WRF model to provide the best input to three different CALMET horizontal resolutions, 1x1 km 2 , 0.5x0.5 km 2 , and 0.2x0.2 km 2 . The best results, very similar between them, were achieved using the last two resolutions; therefore, the 0.5x0.5 km 2 resolution was selected to test different CALMET meteorological inputs, using several combinations of WRF outputs and/or surface and upper-air measurements available in the simulation domain. With respect to meteorological aloft models output, CALMET PBL depth estimations are very similar to PBL depth estimations using upper-air measurements (rawinsondes), and significantly better than WRF PBL depth results. Regarding surface models surface output, the available meteorological sites were divided in two groups, one to provide meteorological input to CALMET (when applied), and another to models validation. Comparing WRF and CALMET outputs against surface measurements (from sites for models validation) the lowest RMSE was achieved using as CALMET input dataset WRF output combined with surface measurements (from sites for

A database for human performance under simulated emergencies of nuclear power plants

International Nuclear Information System (INIS)

Park, Jin Kyun; Jung, Won Dea

2005-01-01

Reliable human performance is a prerequisite in securing the safety of complicated process systems such as nuclear power plants. However, the amount of available knowledge that can explain why operators deviate from an expected performance level is so small because of the infrequency of real accidents. Therefore, in this study, a database that contains a set of useful information extracted from simulated emergencies was developed in order to provide important clues for understanding the change of operators' performance under stressful conditions (i.e., real accidents). The database was developed under Microsoft Windows TM environment using Microsoft Access 97 TM and Microsoft Visual Basic 6.0 TM . In the database, operators' performance data obtained from the analysis of over 100 audio-visual records for simulated emergencies were stored using twenty kinds of distinctive data fields. A total of ten kinds of operators' performance data are available from the developed database. Although it is still difficult to predict operators' performance under stressful conditions based on the results of simulated emergencies, simulation studies remain the most feasible way to scrutinize performance. Accordingly, it is expected that the performance data of this study will provide a concrete foundation for understanding the change of operators' performance in emergency situations

Chemistry in power plants 2011

International Nuclear Information System (INIS)

2011-01-01

Within the VGB Powertech conference from 25th to 27th October, 2011, in Munich (Federal Republic of Germany), the following lectures and poster contributions were presented: (1) The revised VGB standard for water-steam-cycle Chemistry; (2) Switchover from neutral operation to oxygen treatment at the power station Stuttgart-Muenster of EnBW Kraftwerke AG; (3) Steam contamination with degradation products of organic matters present in the feedwater of the Lanxess-Rubber cogeneration plant; (4) Laboratory scale on-line noble metal deposition experiments simulating BWR plant conditions; (5) Building a new demin installation for the power plant EPZ in Borssele; (6) Replacement of the cooling tower installations in the nuclear power plant Goesgen-Daenien AG; (7) Aging of IEX resins in demin plants - Cost optimisation by adaptation of regenerants; (8) The largest DOW trademark EDI System at a combined cycled plant in Europe; (9) Upgrading river Main water to boiler feed water - Experiences with ultrafiltration; (10) Experiences with treatment of the water-steam-cycle in the RDF power plant Nehlsen Stavenhagen with film-forming amines; (11) Comparative modelling of the bubbles thermal collapse and cavitations for estimation of bubbles collapse influence; (12) Overcoming the steam quality - issues from an HRSG for the production of process steam; (13) Legionella - new requirements for power plant operation; (14) How the right chemistry in the FGD helps to improve the removal in the waste water treatment plant; (15) High efficiency filtration in dry/semi-dry FGD plants; (16) Expanding the variety of renewable fuels in the biomass power plant Timelkam using the chemical input control; (17) Corrosion, operating experiences and process improvements to increase the availability and operating time of the biomass power plant Timelkam; (18) The influence of temperature on the measurement of the conductivity of highly diluted solutions; (19) A multiparameter instrumentation approach

Selection, specification, design and use of various nuclear power plant training simulators. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

1998-01-01

Several IAEA publications consider the role of training and particularly the role of simulator training to enhance the safety of NPP operations. Initially, the focus was on full scope simulators for the training of main control room operators. Experience shows that other types of simulator are also effective tools that allow simulator training for a broader range of target groups and training objectives. This report provides guidance to training centers and suppliers on the proper selection, specification, design and use of various forms of simulators. In addition, it provides examples of their use in several Member States. This report is the result of a series of advisory and consultants meetings held in the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) in 1995-1996

Method and system of simulating nuclear power plant count rate for training purposes

International Nuclear Information System (INIS)

Alliston, W.H.; Koenig, R.H.

1975-01-01

A method and system are described for the real-time simulation of the dynamic operation of a nuclear power plant in which nuclear flux rate counters are provided for monitoring the rate of nuclear fission of the reactor. The system utilizes apparatus that includes digital computer means for calculating data relating to the rate of nuclear fission of a simulated reactor model, which rate is controlled in accordance with the operation of control panel devices. A digital number from the computer corresponding to the flux rate controls an oscillator driven counter means to produce a pulse after a predetermined count. This pulse controls an oscillator driven polynomial counter to count a random number that controls a third counter in accordance with pulse from the first counter to produce a random fission count for operating the meters. (U.S.)

Design of power control system using SMES and SVC for fusion power plant

International Nuclear Information System (INIS)

Niiyama, K; Yagai, T; Tsuda, M; Hamajima, T

2008-01-01

A SMES (Superconducting Magnetic Energy Storage System) system with converter composed of self-commutated valve devices such as GTO and IGBT is available to control active and reactive power simultaneously. A SVC (Static Var Compensators) or STATCOM (Static Synchronous Compensator) is widely employed to reduce reactive power in power plants and substations. Owing to progress of power electronics technology using GTO and IGBT devices, power converters in the SMES system and the SVC can easily control power flow in few milliseconds. Moreover, since the valve devices for the SMES are equivalent to those for the SVC, the device cost must be reduced. In this paper the basic control system combined with the SMES and SVC is designed for large pulsed loads of a nuclear fusion power plant. This combined system largely expands the reactive power control region as well as the active one. The simulation results show that the combined system is effective and prospective for the nuclear fusion power plant

Dynamic simulation of operating cases and malfunctions of an IGCC power plant system

Energy Technology Data Exchange (ETDEWEB)

Koch, I.; Hannemann, F. [Siemens AG, Power Generation (KWU), Erlangen (Germany); Hoffmann, U. [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Chemische Verfahrenstechnik

1999-07-01

Fully integrated IGCC plants consist of several units. This novel integration of various plant systems places stiff new requirements on power plant design, as prediction of operating and faulted behavior is made more difficult by many different interactions. This is especially the case for the gas turbine fuel system in an IGCC power plant, as it affects and is affected by all of the other major plant systems. (orig.)

Introducing PCTRAN as an evaluation tool for nuclear power plant emergency responses

International Nuclear Information System (INIS)

Cheng, Yi-Hsiang; Shih, Chunkuan; Chiang, Show-Chyuan; Weng, Tung-Li

2012-01-01

Highlights: ► PCTRAN is integrated with an atmospheric dispersion algorithm. ► The improved PCTRAN acts as an accident/incident simulator and a data exchange system. ► The software helps the responsible organizations decide the rescue and protective actions. ► The evaluation results show the nuclear power plant accident and its off-site dose consequences. ► The software can be used for nuclear power plant emergency responses. - Abstract: Protecting the public from radiation exposure is important if a nuclear power plant (NPP) accident occurs. Deciding appropriate protective actions in a timely and effective manner can be fulfilled by using an effective accident evaluation tool. In our earlier work, we have integrated PCTRAN (Personal Computer Transient Analyzer) with the off-site dose calculation model. In this study, we introduce PCTRAN as an evaluation tool for nuclear power plant emergency responses. If abnormal conditions in the plant are monitored or observed, the plant staffs can distinguish accident/incident initiation events. Thus, the responsible personnel can immediately operate PCTRAN and set up those accident/incident initiation events to simulate the nuclear power plant transient or accident in conjunction with off-site dose distributions. The evaluation results consequently help the responsible organizations decide the rescue and protective actions. In this study, we explain and demonstrate the capabilities of PCTRAN for nuclear emergency responses, through applying it to simulate the postulated nuclear power plant accident scenarios.

Economic Optimization of a Concentrating Solar Power Plant with Molten-salt Thermocline Storage

OpenAIRE

Flueckiger, S. M.; Iverson, B. D.; Garimella, S V

2014-01-01

System-level simulation of a molten-salt thermocline tank is undertaken in response to year-long historical weather data and corresponding plant control. Such a simulation is enabled by combining a finite-volume model of the tank that includes a sufficiently faithful representation at low computation cost with a system-level power tower plant model. Annual plant performance of a 100 MWe molten-salt power tower plant is optimized as a function of the thermocline tank size and the plant solar m...

Development of nuclear power plant operator simulator for man-machine interface evaluation

International Nuclear Information System (INIS)

Nakagawa, Takashi; Nakatani, Yoshio; Sasaki, Kazunori; Yoshikawa, Hidekazu; Takahashi, Makoto; Furuta, Tomihiko; Hasegawa, Akira.

1997-01-01

The operational safety in nuclear power plants depends strongly on man machine interfaces (MMI), such as assignment of equipment on control boards and operation procedures in emergency situations. Therefore, the evaluation and analysis methods for the MMI are important. In order for the methods to be practical, the methods should be executed in each step of design and be easy for designers to use. We aim to develop SEAMAID system: a computer supported system for evaluating and analyzing the MMI by simulating the interaction between the operator and the machine. In this paper, we discuss problems of the conventional methods and the required functions of the operator simulator for the SEAMAID. The operator simulator executes not human errors but correct behavior which follows the operational procedure. The SEAMAID evaluates the MMI by finding potential human errors which could occur in the simulated interactions and points out the problematic interaction parts which could induce human errors. We construct the operator simulator by combining the human model which was proposed by Prof. Reason, and the knowledge base model based on the Petri net model. This simulator can treat frequency parameter which represents the degree of frequency of using a certain knowledge. We conduct two sample simulations in different frequency parameters in the same scenario. These simulation results show that even if the operator behaves correctly following the procedure, there are alternative task sequences. We verify that the simulated interactions are in good agreement with the actual one. Also, we propose the method to point out the problematic parts in the interactions based on the working memory consumption. (author)

Development of nuclear power plant operator simulator for man-machine interface evaluation

Energy Technology Data Exchange (ETDEWEB)

Nakagawa, Takashi; Nakatani, Yoshio; Sasaki, Kazunori [Mitsubishi Electric Corp., Amagasaki, Hyogo (Japan). Industrial Electronics and Systems Development Lab.; Yoshikawa, Hidekazu; Takahashi, Makoto; Furuta, Tomihiko; Hasegawa, Akira

1997-08-01

The operational safety in nuclear power plants depends strongly on man machine interfaces (MMI), such as assignment of equipment on control boards and operation procedures in emergency situations. Therefore, the evaluation and analysis methods for the MMI are important. In order for the methods to be practical, the methods should be executed in each step of design and be easy for designers to use. We aim to develop SEAMAID system: a computer supported system for evaluating and analyzing the MMI by simulating the interaction between the operator and the machine. In this paper, we discuss problems of the conventional methods and the required functions of the operator simulator for the SEAMAID. The operator simulator executes not human errors but correct behavior which follows the operational procedure. The SEAMAID evaluates the MMI by finding potential human errors which could occur in the simulated interactions and points out the problematic interaction parts which could induce human errors. We construct the operator simulator by combining the human model which was proposed by Prof. Reason, and the knowledge base model based on the Petri net model. This simulator can treat frequency parameter which represents the degree of frequency of using a certain knowledge. We conduct two sample simulations in different frequency parameters in the same scenario. These simulation results show that even if the operator behaves correctly following the procedure, there are alternative task sequences. We verify that the simulated interactions are in good agreement with the actual one. Also, we propose the method to point out the problematic parts in the interactions based on the working memory consumption. (author)

Autonomous hydrogen power plants with renewable energy sources

International Nuclear Information System (INIS)

Popel', O.S.; Frid, S.E.; Shpil'rajn, Eh.Eh.; Izosimov, D.B.; Tumanov, V.L.

2006-01-01

One studies the principles to design independent hydrogen power plants (IHPP) operating on renewable energy sources and the approaches to design a pilot IHP plant. One worded tasks of mathematical simulation and of calculations to substantiate the optimal configuration of the mentioned plants depending on the ambient conditions of operation and on peculiar features of a consumer [ru

Design and static simulation of secondary loop of small PWR nuclear power plants

International Nuclear Information System (INIS)

Martin Lopez, L.A.N.

1989-01-01

A computer program that has been developed with the purpose of making easier the decisions concerning the design of the secondary loop of small PWR nuclear power plants through numerical experiments of low running costs and short time is presented. Initially, the first part of the computer program is described. It aims to preliminarily design several major components of the secondary circuit from user-defined design conditions. Next, the second part of the computer program is presented. It simulates the steady state operation at part-load conditions of the preliminary design of the plant by generating and solving systems of simultaneous nonlinear algebraic equations, their number varying from 17 to 107. The computer program has been tested for several application cases. The program results are discussed in the last part of the work, along with several aspects to be added to the program in future works. (author)

Plant analyzer for high-speed interactive simulation of BWR plant transients

International Nuclear Information System (INIS)

Cheng, H.S.; Lekach, S.V.; Mallen, A.N.; Wulff, W.; Cerbone, R.J.

1984-01-01

A combination of advanced modeling techniques and modern, special-purpose peripheral minicomputer technology was utilized to develop a plant analyzer which affords realistic predictions of plant transients and severe off-normal events in LWR power plants through on-line simulations at speeds up to 10 times faster than actual process speeds. The mathematical models account for nonequilibrium, nonhomogeneous two-phase flow effects in the coolant, for acoustical effects in the steam line and for the dynamics of the entire balance of the plant. Reactor core models include point kinetics with reactivity feedback due to void fraction, fuel temperature, coolant temperature, and boron concentration as well as a conduction model for predicting fuel and clad temperatures. Control systems and trip logic for plant protection systems are also simulated. The AD10 of Applied Dynamics International, a special-purpose peripheral processor, is used as the principal hardware of the plant analyzer

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

Integration of torrefaction with steam power plant

Energy Technology Data Exchange (ETDEWEB)

Zakri, B.; Saari, J.; Sermyagina, E.; Vakkilainen, E.

2013-09-01

Torrefaction is one of the pretreatment technologies to enhance the fuel characteristics of biomass. The efficient and continuous operation of a torrefaction reactor, in the commercial scale, demands a secure biomass supply, in addition to adequate source of heat. Biorefinery plants or biomass-fuelled steam power plants have the potential to integrate with the torrefaction reactor to exchange heat and mass, using available infrastructure and energy sources. The technical feasibility of this integration is examined in this study. A new model for the torrefaction process is introduced and verified by the available experimental data. The torrefaction model is then integrated in different steam power plants to simulate possible mass and energy exchange between the reactor and the plants. The performance of the integrated plant is investigated for different configurations and the results are compared. (orig.)

Impact of Wind Power Plants on Voltage Control of Power System

DEFF Research Database (Denmark)

Sarkar, Moumita; Altin, Müfit; Hansen, Anca Daniela

High penetration of renewable energy sources poses numerous challenges on stability and security of power systems. Wind power plants (WPPs) of considerable size when connected to a weak grid by long transmission line results in low short circuit ratio at the point of connection. This may result...... control, during transient voltage dips. Steady-state analysis is performed for stressed system conditions. Results are validated through simulation in a detailed power system model....

Full scope simulator of a nuclear power plant control room using 3D stereo virtual reality techniques for operators training

International Nuclear Information System (INIS)

Aghina, Mauricio A.C.; Mol, Antonio Carlos A.; Almeida, Adino Americo A.; Pereira, Claudio M.N.A.; Varela, Thiago F.B.

2007-01-01

Practical training of nuclear power plants operators are partially performed by means of simulators. Usually these simulators are physical copies of the original control roam, needing a large space on a facility being also very expensive. In this way, the proposal of this paper is to implement the use of Virtual Reality techniques to design a full scope control room simulator, in a manner to reduce costs and physical space usage. (author)

A study on advanced man-machine interface system for autonomous nuclear power plants

International Nuclear Information System (INIS)

Matsuoka, Takeshi; Numano, Masayoshi; Fukuto, Junji; Sugasawa, Shinobu; Miyazaki, Keiko; Someya, Minoru; Haraki, Nobuo

1994-01-01

A man-machine interface(MMI) system of an autonomous nuclear power plant has an advanced function compared with that of the present nuclear power plants. The MMI has a function model of a plant state, and updates and revises this function model by itself. This paper describes the concept of autonomous nuclear power plants, a plant simulator of an autonomous power plant, a contracted function model of a plant state, three-dimensional color graphic display of a plant state, and an event-tree like expression for plant states. (author)

Kansas Power Plants

Data.gov (United States)

Kansas Data Access and Support Center — The Kansas Power Plants database depicts, as point features, the locations of the various types of power plant locations in Kansas. The locations of the power plants...

Plant simulator

International Nuclear Information System (INIS)

Fukumitsu, Hiroyuki

1998-01-01

A simulator of a reactor plant of the present invention comprises a plurality of distributed computers, an indication processing section and an operation section. The simulation calculation functions of various kinds of plant models in the plant are shared by the plurality of computers. The indication processing section controls collection of data of the plant simulated by the computers and instructions of an operator. The operation section is operated by the operator and the results of operation are transmitted to the indication processing section, to conduct operation trainings and display the results of the simulation. Each of the computers and the indication processing portion are connected with each other by a network having a memory for common use. Data such as the results of calculation of plant models and various kinds of parameters of the plant required commonly to the calculators and the indication processing section are stored in the common memory, and adapted to be used by way of the network. (N.H.)

Numerical analysis on the performance of solar chimney power plant system

International Nuclear Information System (INIS)

Xu Guoliang; Ming Tingzhen; Pan Yuan; Meng Fanlong; Zhou Cheng

2011-01-01

Power generating technology based on renewable energy resources will definitely become a new trend of future energy utilization. Numerical simulations on air flow, heat transfer and power output characteristics of a solar chimney power plant model with energy storage layer and turbine similar to the Spanish prototype were carried out in this paper, and mathematical model of flow and heat transfer for the solar chimney power plant system was established. The influences of solar radiation and pressure drop across the turbine on the flow and heat transfer, output power and energy loss of the solar chimney power plant system were analyzed. The numerical simulation results reveal that: when the solar radiation and the turbine efficiency are 600 W/m 2 and 80%, respectively, the output power of the system can reach 120 kW. In addition, large mass flow rate of air flowing through the chimney outlet become the main cause of energy loss in the system, and the collector canopy also results in large energy loss.

Computer code to simulate transients in a steam generator of PWR nuclear power plants

International Nuclear Information System (INIS)

Silva, J.M. da.

1979-01-01

A digital computer code KIBE was developed to simulate the transient behavior of a Steam Generator used in Pressurized Water Reactor Power PLants. The equations of Conservation of mass, energy and momentum were numerically integrated by an implicit method progressively in the several axial sections into which the Steam Generator was divided. Forced convection heat transfer was assumed on the primary side, while on the secondary side all the different modes of heat transfer were permitted and deternined from the various correlations. The stability of the stationary state was verified by its reproducibility during the integration of the conservation equation without any pertubation. Transient behavior resulting from pertubations in the flow and the internal energy (temperature) at the inlet of the primary side were simulated. The results obtained exhibited satisfactory behaviour. (author) [pt

Simulation of a postulated 2% cold leg break in Angra 2 nuclear power plant

International Nuclear Information System (INIS)

Palmieiri, Elcio Tadeu; Azevedo, Carlos Vicente Goulart de; Aronne, Ivan Dionysio

2007-01-01

This paper presents the simulation of a 2% break in the cold leg pipe of Angra 2 nuclear power plant, with the computer code RELAP5/Mod3.3. The main boundary conditions specified for this simulation were: no injection from high pressure injection system; enhanced depressurization of the primary system by opening the pressure operated relief valve (PORV) and the safety relief valve (SRV) when core temperature reaches circa 100 K above saturation; and accumulator injection starting at 2.7 MPa. The specific objectives to be addressed with this simulation are: the core boil-off and dryout at relatively high pressure in the primary system; the phenomena during enhanced primary depressurization; the effectiveness of hot leg accumulator injection into the partially uncovered rod bundle; and the core rewetting. The results obtained were compared with the Lobi A1-93 test, which was performed under the same boundary conditions. This activity was executed in the scope of IAEA research project Evaluation of Uncertainties in the Simulation of Accidents in Angra 2 using RELAP5/MOD3 Code Applying CIAU Methodology (author)

Development of AI (Artificial Intelligence)-based simulation system for man-machine system behavior in accidental situations of nuclear power plant

International Nuclear Information System (INIS)

Yoshida, Kazuo; Yokobayashi, Masao; Tanabe, Fumiya; Kawase, Katumi.

1996-01-01

A prototype version of a computer simulation system named JACOS (JAeri COgnitive Simulation system) has been developed at JAERI (Japan Atomic Energy Research Institute) to simulate the man-machine system behavior in which both the cognitive behavior of a human operator and the plant behavior affect each other. The objectives of this system development is to provide man-machine system analysts with detailed information on the cognitive process of an operator and the plant behavior affected by operator's actions in accidental situations of an NPP (nuclear power plant). The simulation system consists of an operator model and a plant model which are coupled dynamically. The operator model simulates an operator's cognitive behavior in accidental situations based on the decision ladder model of Rasmussen, and is implemented using the AI-techniques of the distributed cooperative inference method with the so-called blackboard architecture. Rule-based behavior is simulated using knowledge representation with If-Then type of rules. Knowledge-based behavior is simulated using knowledge representation with MFM (Multilevel Flow Modeling) and qualitative reasoning method. Cognitive characteristics of attentional narrowing, limitation of short-term memory, and knowledge recalling from long-term memory are also modeled. The plant model of a 3-loop PWR is also developed using a best estimate thermal-hydraulic analysis code RELAP5/MOD2. Some simulations of incidents were performed to verify the human model. It was found that AI-techniques used in the human model are suitable to simulate the operator's cognitive behavior in an NPP accident. The models of cognitive characteristics were investigated in the effects on simulated results of cognitive behaviors. (author)

Hydroelectric Power Plants Dobsina

International Nuclear Information System (INIS)

Majercak, V.; Srenkelova, Z.; Kristak, J.G.

1997-01-01

In this brochure the Hydroelectric Power Plants Dobsina, (VED), subsidiary of the utility Slovenske Elektrarne, a.s. (Slovak Electric, plc. Bratislava) are presented. VED is mainly aimed at generating peak-load electrical energy and maintenance of operational equipment. Reaching its goals, company is first of all focused on reliability of production, economy and effectiveness, keeping principles of work safety and industry safety standards and also ecology. VED operates eight hydroelectric power plants, from which PVE Ruzin I and PVE Dobsina I are pump storage ones and they are controlled directly by the Slovak Energy Dispatch Centre located in Zilina thought the system LS 3200. Those power plants participate in secondary regulation of electrical network of Slovakia. They are used to compensate balance in reference to foreign electrical networks and they are put into operation independently from VED. Activity of the branch is focused mainly on support of fulfilment of such an important aim as electric network regulation. Beginnings of the subsidiary Hydroelectric Power Plants Dobsina are related to the year of 1948. After commissioning of the pump storage Hydroelectric Power Plants Dobsina in 1953, the plant started to carry out its mission. Since that time the subsidiary has been enlarged by other seven power plants, through which it is fulfilling its missions nowadays. The characteristics of these hydroelectric power plants (The pump-storage power plant Dobsina, Small hydroelectric power plant Dobsina II, Small hydroelectric power plant Rakovec, Small hydroelectric power plant Svedlar, Hydroelectric power plant Domasa, The pump-storage power plant Ruzin, and Small hydroelectric power plant Krompachy) are described in detail. Employees welfare and public relations are presented

Digital I and C system pre-tests using plant specific simulators

International Nuclear Information System (INIS)

Holl, B.; Probst, H.; Wischert, W.

2006-01-01

The paper focuses on strategic aspects of the implementation of modern digital instrumentation and control system (I and C) in nuclear power plant (NPP) training simulators and points out the way to identify the most appropriate implementation method of the digital I and C system in the simulator development environment which fulfils the requirement imposed by the nuclear power plants. This regards mainly training aspects, simulator as a test bed for design verification and validation (V and V), and software maintenance aspects with respect to future evolutions of the digital I and C system. (author)

Development of user interface to support automatic program generation of nuclear power plant analysis by module-based simulation system

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu; Mizutani, Naoki; Nakaya, Ken-ichiro; Wakabayashi, Jiro

1988-01-01

Module-based Simulation System (MSS) has been developed to realize a new software work environment enabling versatile dynamic simulation of a complex nuclear power system flexibly. The MSS makes full use of modern software technology to replace a large fraction of human software works in complex, large-scale program development by computer automation. Fundamental methods utilized in MSS and developmental study on human interface system SESS-1 to help users in generating integrated simulation programs automatically are summarized as follows: (1) To enhance usability and 'communality' of program resources, the basic mathematical models of common usage in nuclear power plant analysis are programed as 'modules' and stored in a module library. The information on usage of individual modules are stored in module database with easy registration, update and retrieval by the interactive management system. (2) Target simulation programs and the input/output files are automatically generated with simple block-wise languages by a precompiler system for module integration purpose. (3) Working time for program development and analysis in an example study of an LMFBR plant thermal-hydraulic transient analysis was demonstrated to be remarkably shortened, with the introduction of an interface system SESS-1 developed as an automatic program generation environment. (author)

Comparative studies between nuclear power plants and hydroelectric power plants

International Nuclear Information System (INIS)

Menegassi, J.

1984-01-01

This paper shows the quantitative evolution of the power plants in the main countries of the world. The Brazilian situation is analysed, with emphasys in the technical and economical aspects related to power production by hidroelectric or nuclear power plants. The conclusion is that the electricity produced by hidro power plants becomes not economics when is intended to be produced at large distances from the demand centers. (Author) [pt

Design of Simulation Product for Stability of Electric Power System Using Power System Stabilizer and Optimal Control

Science.gov (United States)

Junaidi, Agus; Hamid, K. Abdul

2018-03-01

This paper will discuss the use of optimal control and Power System Stabilizer (PSS) in improving the oscillation of electric power system. Oscillations in the electric power system can occur due to the sudden release of the load (Switcing-Off). The oscillation of an unstable system for a long time causes the equipment to work in an interruption. To overcome this problem, a control device is required that can work effectively in repairing the oscillation. The power system is modeled from the Single Machine Infinite Bus Model (SMIB). The state space equation is used to mathematically model SMIB. SMIB system which is a plant will be formed togetherness state variables (State-Space), using riccati equation then determined the optimal gain as controller plant. Plant is also controlled by Power Stabilizer System using phase compensation method. Using Matlab Software based simulation will be observed response of rotor speed change and rotor angle change for each of the two controlling methods. Simulation results using the Simulink-MATLAB 6.1 software will compare the analysis of the plant state in Open loop state and use the controller. The simulation response shows that the optimal control and PSS can improve the stability of the power system in terms of acceleration to achieve settling-time and Over Shoot improvement. From the results of both methods are able to improve system performance.

Implementation of nuclear power plant simulation in start-up commissioning of reactor control system

International Nuclear Information System (INIS)

Yang Zongwei; Huang Tieming; Feng Guangyu; Luan Zhenhua; Lin Meng; Zhu Lizhi

2009-01-01

Based on the nuclear power thermal-hydraulic model, Labview graphical programming language and virtual instrument data acquisition technology, this paper describes a dedicate test platform to solve the problem that the reactor control system (RRC) can not be evaluated and analyzed far before the actual startup of the unit. By connecting the test platform to the nuclear Digital Control System (DCS), the step-by-step closed-looped test and global function test of RRC system were performed, the dynamic validation and logical function demonstration for RRC were realized, and a lot of configuration mistakes of RRC and nonconformity were solved. The test for unit 3 of Ling'ao phase II has proved that the implementation of nuclear power plant simulation in the start-up commissioning of RRC can greatly reduce the risk of normal power operation and great transient tests, with which the term of startup for overall unit test can be greatly shortened. (authors)

Modelling and Simulation of VSC-HVDC Connection for Offshore Wind Power Plants

DEFF Research Database (Denmark)

Chaudhary, Sanjay Kumar; Teodorescu, Remus; Rodriguez, Pedro

2010-01-01

Several large offshore wind power plants (WPP) are planned in the seas around Europe. VSC-HVDC is a suitable means of integrating such large and distant offshore WPP which need long submarine cable transmission to the onshore grid. Recent trend is to use large wind turbine generators with full...... scale converters to achieve an optimal operation over a wide speed range. The offshore grid then becomes very much different from the conventional power system grid, in the sense that it is connected to power electronic converters only. A model of the wind power plant with VSC-HVDC connection...

Impact of external grid disturbances on nuclear power plants; Rueckwirkungen von Netzstoerungen auf Kernkraftwerke

Energy Technology Data Exchange (ETDEWEB)

Arains, Robert; Arnold, Simone; Brueck, Benjamin; Mueller, Christian; Quester, Claudia; Sommer, Dagmar

2017-06-15

The electrical design of nuclear power plants and the reliability of their electrical power supply including the offsite power supply are of high importance for the safe operation of the plants. The operating experience of recent years has shown that disturbances in the external grid can have impact on the electrical equipment of nuclear power plants. In the course of this project, possible causes and types of grid disturbances were identified. Based on these, scenarios of grid disturbances were developed. In order to investigate the impact of the developed scenarios of grid disturbances on the electrical equipment of nuclear power plants, the auxiliary power supply of a German pressurized water reactor of type Konvoi was simulated using the simulation tool NEPLAN. On the basis of the results of the analyses, it was identified whether there are possible measures to prevent the spread of grid disturbances in the plants which have not been implemented in the nuclear power plants today.

Contribution to the modeling and simulation of solar power tower plants using energy analysis

International Nuclear Information System (INIS)

Benammar, S.; Khellaf, A.; Mohammedi, K.

2014-01-01

Highlights: • The solar tower power plant system (STPP) is divided into four main subsystems. • The energy balance of each subsystem has been developed. • A general nonlinear mathematical model of the studied system (STPP) has been presented. • Using numerical optimization methods, the nonlinear mathematical model has been solved. • The obtained results are presented and analyzed. - Abstract: In this paper, a mathematical model based on energy analysis, has been developed for modeling and simulation of solar tower power plants (STPP) performances without energy storage. The STPP system has been divided into four main subsystems: the heliostat field subsystem, the cavity receiver subsystem (tower), the steam generation subsystem and the power cycle subsystem (Rankine cycle). Thermal and thermodynamic models of main subsystems have been developed. A general nonlinear mathematical model of the studied system (STPP) has been presented and solved using numerical optimization methods. The obtained results are presented and analyzed. The effects of the receiver surface temperature and the receiver surface area on the cavity receiver efficiency and the steam mass flow have been investigated. The effects of other parameters, such as the incident heat flux, the absorbed energy and the heat losses from the receiver are also studied. The analysis of these results shows the existence of an optimal receiver efficiency value for each steam mass flow, receiver surface temperature and receiver surface area

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

International Nuclear Information System (INIS)

Ichiki, Tadaharu; Tanaka, Masayuki.

1991-01-01

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

Support services for new nuclear power plant projects

International Nuclear Information System (INIS)

Manrique, Alberto B.; Cazorla, Francisco

2009-01-01

TECNATOM is a spanish engineering company with more than 50 years of experience working for the nuclear industry all over the world. TECNATOM has worked in over 30 countries in activities related to the Operation and Maintenance of Nuclear Power Plants. It started to work in the design of new Nuclear Power Plants in the early 90s and since then has continued collaborating with different suppliers in the design and licensing of new reactors specially in the areas of plant systems design, Man-Machine Interface design, Main Control Room simulators building, training, qualification of equipment and PSI/ISI engineering services. (author)

Design and simulation of a geothermal–solar combined chimney power plant

International Nuclear Information System (INIS)

Cao, Fei; Li, Huashan; Ma, Qiuming; Zhao, Liang

2014-01-01

Highlights: • A geothermal–solar chimney power plant (GSCPP) is designed and analyzed. • Three different models, viz. full solar model, full geothermal model and geothermal–solar mode are compared. • Power generation under GSM is larger than the sum of FSM and FGM. • GSCPP can effectively solve the continuous operation problem of the SCPP. - Abstract: The solar chimney power plant (SCPP) is dominated by the solar radiation, and therefore its discontinuous operation is an unavoidable problem. In this paper, low temperature geothermal water is introduced into the SCPP for overcoming this problem. Based on a developed transient model, theoretical analyses are carried out to investigate the performance of the geothermal–solar chimney power plant (GSCPP) with main dimensions the same as the Manzanares prototype in Spain. Three operation models, viz. the full solar model, the full geothermal model and the geothermal–solar combined model are compared in typical summer and winter days and throughout the year. It is found that the GSCPP can attractively run in the GSM to deliver power continuously. Due to the ambient-dependant geothermal water outlet temperature, introducing the geothermal water makes greater contribution in winter days than in summer days, in the night than in the daytime. Power generation under GSM is larger than the sum of FSM and FGM. GSM is not the simple superposition of FSM and FGM, but makes better utilization of solar and geothermal energy. In addition, introducing high temperature and mass flow rate geothermal water can doubled and redoubled improve the GSCPP’s power capacity

Relay Protection Coordination for Photovoltaic Power Plant Connected on Distribution Network

OpenAIRE

Nikolovski, Srete; Papuga, Vanja; Knežević, Goran

2014-01-01

This paper presents a procedure and computation of relay protection coordination for a PV power plant connected to the distribution network. In recent years, the growing concern for environment preservation has caused expansion of photovoltaic PV power plants in distribution networks. Numerical computer simulation is an indispensable tool for studying photovoltaic (PV) systems protection coordination. In this paper, EasyPower computer program is used with the module Power Protector. Time-curr...

Nonlinear Fuzzy Model Predictive Control for a PWR Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Xiangjie Liu

2014-01-01

Full Text Available Reliable power and temperature control in pressurized water reactor (PWR nuclear power plant is necessary to guarantee high efficiency and plant safety. Since the nuclear plants are quite nonlinear, the paper presents nonlinear fuzzy model predictive control (MPC, by incorporating the realistic constraints, to realize the plant optimization. T-S fuzzy modeling on nuclear power plant is utilized to approximate the nonlinear plant, based on which the nonlinear MPC controller is devised via parallel distributed compensation (PDC scheme in order to solve the nonlinear constraint optimization problem. Improved performance compared to the traditional PID controller for a TMI-type PWR is obtained in the simulation.

Development of a Nuclear Steam Supply System Thermal-Hydraulic Module for the Nuclear Power Plant Simulator Using a Best-Estimate Code, RETRAN

International Nuclear Information System (INIS)

Suh, Jae Seung

2004-08-01

The NSSS (Nuclear Steam Supply System) thermal-hydraulic programs adopted in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually used very simplified physical models for the real-time simulation of Ness thermal-hydraulic transients, which entails inaccurate results and, thus, the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, a realistic NSSS thermal-hydraulic program ARTS has been developed, it was based on the RETRAN code for the improvement of the Nuclear Power Plant full-scope simulator. Since ARTS is a generalized code to solve a simultaneous equation system, the smaller time-step size should be used if converged solution could not obtain even in a single volume. Therefore, dedicated models which do not force to reduce the time-step size are sometimes more suitable in terms of a real-time calculation and robustness. The PRT(Pressurizer Relief Tank) is a good example, which requires a dedicated model. The PRT consists of subcooled water in bottom and non-condensable gas in top. The sparger merged under subcooled water enhances condensation. The complicated thermal-hydraulic phenomena such as condensation, phase separation with existence of non-condensable gas makes difficult to simulate. Therefore, the PRT volume may limit the time-step size if it is modeled with a general control volume. To mitigate the time-step size reduction due to convergence failure at this component using RETRAN, the PRT model was developed as a dedicated model. The dedicated model was expected to provide reasonable results without convergence problem in the analysis of the system transients. The ARTS code guarantees the real-time calculations of almost all transients and ensures the robustness of simulations. However, there are some possibilities of calculation failure in the

Closure simulation of the MSIV of Unit 1 of the Laguna Verde nuclear power plant using the Simulate 3K code

International Nuclear Information System (INIS)

Alegria A, A.

2015-09-01

In this paper the simulation of closure transient of all main steam isolation valves (MSIV) was performed with the Simulate-3K (S-3K) code for the Unit 1 of the Laguna Verde nuclear power plant (NPP-LV), which operates to thermal power of 2317 MWt, corresponding to the cycle 15 of operation. The set points for the performance of systems correspond to those set out in transient analysis: 3 seconds for the closure of all MSIV; the start of Scram when 121% of the neutron flux is reached, respect from baseline before the transient; the opening by peer of safety relief valves (SRV) in relief mode when the set point of the pressure is reached, the shoot of the feedwater flow seconds after the start of closing of the MSIV and the shoot of the recirculation water pumps when the pressure is reached in the dome of 1048 psig. The simulation time was of 57 seconds, with the top 50 to reach the steady state, from which the closure of all MSIV starts. In this paper the behavior of the pressure in the dome are analyzed, thermal power, neutron flux, the collapsed water level, the flow at the entrance of core, the steam flow coming out of vessel and the flow through of the SRV; the fuel temperature, the minimal critical power ratio, the readings in the instrumentation systems and reactivities. Instrumentation systems were implemented to analyze the neutron flux, these consist of 96 local power range monitors (LPRM) located in different radial and axial positions of the core and 4 channels of average power range monitors, which grouped at 24 LPRM each one. LPRM response to the change of neutron flux in the center of the core, at different axial positions is also shown. Finally, the results show that the safety limit MCPR is not exceeded. (Author)

Dynamic simulator for nuclear power plants (DSNP): development, verification, and expansion of modules

International Nuclear Information System (INIS)

Larson, H.A.; Dean, E.M.; Koenig, J.F.; Gale, J.G.; Lehto, W.K.

1984-01-01

The DSNP Simulation Language facilitates whole reactor plant simulation and design. Verification includes DSNP dynamic modeling of Experimental Breeder Reactor No. 2 (EBR-II) plant experiments as well as comparisons with verified simulation programs. Great flexibility is allowed in expanding the DSNP language and accommodate other computer languages. The component modules of DSNP, contained in libraries, are continually updated with new, improved, and verified modules. The modules are used to simulate the dynamic response of LMFBR reactor systems to upset and transient conditions, with special emphasis on investigations of inherent shutdown mechanisms

Investigation on the dynamic behaviour of a parabolic trough power plant during strongly cloudy days

International Nuclear Information System (INIS)

Al-Maliki, Wisam Abed Kattea; Alobaid, Falah; Starkloff, Ralf; Kez, Vitali; Epple, Bernd

2016-01-01

Highlights: • A detailed dynamic model of a parabolic trough solar thermal power plant is done. • Simulated results are compared to the experimental data from the real power plant. • Discrepancy between model result and real data is caused by operation strategy. • The model strategy increased the operating hours of power plant by around 2.5–3 h. - Abstract: The objective of this study is the development of a full scale dynamic model of a parabolic trough power plant with a thermal storage system, operated by the Actividades de Construcción y Servicios Group in Spain. The model includes solar field, thermal storage system and the power block and describes the heat transfer fluid and steam/water paths in detail. The parabolic trough power plant is modelled using Advanced Process Simulation Software (APROS). To validate the model, the numerical results are compared to the measured data, obtained from “Andasol II” during strongly cloudy periods in the summer days. The comparisons show a qualitative agreement between the dynamic simulation model and the measurements. The results confirm that the thermal storage enables the parabolic trough power plant to provide a constant power rate when the storage energy discharge is available, despite significant oscillations in the solar radiation.

Effect of Low Pressure End Conditions on Steam Power Plant Performance

Directory of Open Access Journals (Sweden)

Ali Syed Haider

2014-07-01

Full Text Available Most of the electricity produced throughout the world today is from steam power plants and improving the performance of power plants is crucial to minimize the greenhouse gas emissions and fuel consumption. Energy efficiency of a thermal power plant strongly depends on its boiler-condenser operating conditions. The low pressure end conditions of a condenser have influence on the power output, steam consumption and efficiency of a plant. Hence, the objective this paper is to study the effect of the low pressure end conditions on a steam power plant performance. For the study each component was modelled thermodynamically. Simulation was done and the results showed that performance of the condenser is highly a function of its pressure which in turn depends on the flow rate and temperature of the cooling water. Furthermore, when the condenser pressure increases both net power output and plant efficiency decrease whereas the steam consumption increases. The results can be used to run a steam power cycle at optimum conditions.

Simulations research of the global predictive control with self-adaptive in the gas turbine of the nuclear power plant

International Nuclear Information System (INIS)

Su Jie; Xia Guoqing; Zhang Wei

2007-01-01

For further improving the dynamic control capabilities of the gas turbine of the nuclear power plant, this paper puts forward to apply the algorithm of global predictive control with self-adaptive in the rotate speed control of the gas turbine, including control structure and the design of controller in the base of expounding the math model of the gas turbine of the nuclear power plant. the simulation results show that the respond of the change of the gas turbine speed under the control algorithm of global predictive control with self-adaptive is ten second faster than that under the PID control algorithm, and the output value of the gas turbine speed under the PID control algorithm is 1%-2% higher than that under the control slgorithm of global predictive control with self-adaptive. It shows that the algorithm of global predictive control with self-adaptive can better control the output of the speed of the gas turbine of the nuclear power plant and get the better control effect. (authors)

Dynamic analysis of Boushehr Nuclear Power Plant in connected to grid system

International Nuclear Information System (INIS)

Karimi Fard, A.

1999-01-01

Models of generating with the pressurized water reactor (PWR) have been developed for simulating. the plant dynamics under system disturbances. These models include power plant, energy sources, turbine, transmission system and control system such as Avr and govern and other local control devices. Simulink toolbox of Matlab software is used for simulations. The study is mainly based on the Bushehr Nuclear Power Plants (BNPP) parameters. Assuming that BNPP is connected to infinite bus with double tie line. Four cases are studied to examine the internal dynamic behavior of BNPP. First and second cases are used to load following studies in nuclear power plant. Another cases are used to study the dynamic behavior after short circuit fault and line outages in transmission systems. The results discussed in the thesis

Description of the power plant model BWR-plasim outlined for the Barsebaeck 2 plant

International Nuclear Information System (INIS)

Christensen, P. la Cour.

1979-08-01

A description is given of a BWR power plant model outlined for the Barsebaeck 2 plant with data placed at our disposal by the Swedish Power Company Sydkraft A/B. The basic operations are derived and simplifications discussed. The model is implemented with a simulation system DYSYS which assures reliable solutions and easy programming. Emphasis has been placed on the models versatility and flexibility so new features are easy to incorporate. The model may be used for transient calculations for both normal plant conditions and for abnormal occurences as well as for control system studies. (author)

Decentralised electrical distribution network in power plants

International Nuclear Information System (INIS)

Mannila, P.; Lehtonen, M.

2000-02-01

A centralised network is a dominating network solution in today's power plants. In this study a centralised and a decentralised network were designed in order to compare them economically and technically. The emphasis of this study was on economical aspects, but also the most important technical aspects were included. The decentralised network requires less space and less cabling since there is no switchgear building and distribution transformers are placed close to the consumption in the field of a power plant. MV-motors and distribution transformers build up a ring. Less cabling and an absent switchgear building cause considerable savings. Component costs of both of the networks were estimated by using data from fulfilled power plant projects and turned out to be smaller for the decentralised network. Simulations for the decentralised network were done in order to find a way to carry out earth fault protection and location. It was found out that in high resistance earthed system the fault distance can be estimated by a relatively simple method. The decentralised network uses a field bus, which offers many new features to the automation system of a power plant. Diversified information can be collected from the protection devices in order to schedule only the needed maintenance duties at the right time. Through the field bus it is also possible to control remotely a power plant. The decentralised network is built up from ready-to-install modules. These modules are tested by the module manufacturer decreasing the need for field testing dramatically. The work contribution needed in the electrification and the management of a power plant project reduces also due the modules. During the lifetime of a power plant, maintenance is easier and more economical. (orig.)

Proceedings of the 2nd CSNI Specialist Meeting on Simulators and Plant Analysers

International Nuclear Information System (INIS)

Tiihonen, O.

1999-01-01

The safe utilisation of nuclear power plants requires the availability of different computerised tools for analysing the plant behaviour and training the plant personnel. These can be grouped into three categories: accident analysis codes, plant analysers and training simulators. The safety analysis of nuclear power plants has traditionally been limited to the worst accident cases expected for the specific plant design. Many accident analysis codes have been developed for different plant types. The scope of the analyses has continuously expanded. The plant analysers are now emerging tools intended for extensive analysis of the plant behaviour using a best estimate model for the whole plant including the reactor and full thermodynamic process, both combined with automation and electrical systems. The comprehensive model is also supported by good visualisation tools. Training simulators with real time plant model are tools for training the plant operators to run the plant. Modern training simulators have also features supporting visualisation of the important phenomena occurring in the plant during transients. The 2nd CSNI Specialist Meeting on Simulators and Plant Analysers in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. (orig.)

Power generation enhancement in a salinity-gradient solar pond power plant using thermoelectric generator

International Nuclear Information System (INIS)

Ziapour, Behrooz M.; Saadat, Mohammad; Palideh, Vahid; Afzal, Sadegh

2017-01-01

Highlights: • Thermoelectric generator was used and simulated within a salinity-gradient solar pond power plant. • Results showed that the thermoelectric generator can be able to enhance the power plant efficiency. • Results showed that the presented models can be able to produce generation even in the cold months. • The optimum size of area of solar pond based on its effect on efficiency is 50,000 m 2 . - Abstract: Salinity-gradient solar pond (SGSP) has been a reliable supply of heat source for power generation when it has been integrated with low temperature thermodynamics cycles like organic Rankine cycle (ORC). Also, thermoelectric generator (TEG) plays a critical role in the production of electricity from renewable energy sources. This paper investigates the potential of thermoelectric generator as a power generation system using heat from SGSP. In this work, thermoelectric generator was used instead of condenser of ORC with the purpose of improving the performance of system. Two new models of SGSP have been presented as: (1) SGSP using TEG in condenser of ORC without heat exchanger and (2) SGSP using TEG in condenser of ORC with heat exchanger. These proposed systems was evaluated through computer simulations. The ambient conditions were collected from beach of Urmia lake in IRAN. Simulation results indicated that, for identical conditions, the model 1 has higher performance than other model 2. For models 1 and 2 in T LCZ = 90 °C, the overall thermal efficiency of the solar pond power plant, were obtained 0.21% and 0.2% more than ORC without TEG, respectively.

Modelling and dynamic simulation of processes with 'MATLAB'. An application of a natural gas installation in a power plant

International Nuclear Information System (INIS)

Gonzalez-Bustamante, J.A.; Sala, J.M.; Lopez-Gonzalez, L.M.; Miguez, J.L.; Flores, I.

2007-01-01

In this paper, it is proposed to incorporate the analysis of the dynamic performance of the process into the design and engineering stage of projects as a means of analysing and resolving this type of problem. The following contributions are made with this objective in mind:(a)The barriers in the way of dynamic analysis are identified. (b)Software tools which make dynamic analysis accessible during the design and engineering phase of the project are proposed. To achieve this goal, modelling and mathematical simulation are used, with the following features: *strict modelling of mass, momentum and energy conservation equations as well as state equations, and *utilisation of the 'Matlab-Simulink' package as the base-software tool. (c)The procedure and tool proposed for dynamic analysis during the design phase should enable these studies to be carried out at a reasonable cost and time for regular industrial projects, and not just for large research projects or nuclear power plants. To complete this paper, we apply our method to a natural gas installation in a power plant. The model is applied to study the transients of a natural gas supply line to a steam-electric power plant. The results of the model have been validated with the actual data on the boiler trip obtained from the distributed control system of a steam-electric power plant