WorldWideScience

Sample records for power plant study

  1. Power Plant Replacement Study

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois University's aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  2. Power Plant Replacement Study

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois University’s aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  3. Westinghouse ICF power plant study

    Sucov, E.W.

    1980-10-01

    In this study, two different electric power plants for the production of about 1000 MWe which were based on a CO 2 laser driver and on a heavy ion driver have been developed and analyzed. The purposes of this study were: (1) to examine in a self consistent way the technological and institutional problems that need to be confronted and solved in order to produce commercially competitive electricity in the 2020 time frame from an inertial fusion reactor, and (2) to compare, on a common basis, the consequences of using two different drivers to initiate the DT fuel pellet explosions. Analytic descriptions of size/performance/cost relationships for each of the subsystems comprising the power plant have been combined into an overall computer code which models the entire plant. This overall model has been used to conduct trade studies which examine the consequences of varying critical design values around the reference point

  4. Comparative studies between nuclear power plants and hydroelectric power plants

    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

  5. Fusion power plant availability study

    Ladra, D.; Sanguinetti, G.P.; Stube, E.

    2001-01-01

    The consideration of fusion as an alternative energy source will need to demonstrate that Fusion Power Plant (FPP) design, operating and maintenance characteristics meet the electrical market requirements forecast for the second half of this century. Until now, fusion has been developed in the framework of research and development programmes following natural technological trends. To bring a greater sense of realism to commercial viability and to guarantee that technology-driven fusion development responds to the demands of the market, a conceptual study of future commercial FPPs has been performed with a Power Plant Availability (PPA) study aimed at identifying the aspects affecting the availability and generating costs of FPPs. EFET, who has also been involved in the study, can visualise it from two different points of view; that of the industry (ANSALDO, IBERTEF, SIEMENS, NNC) and that of the utilities (BELGATOM, FRAMATOME, FORTUM). The work carried out covered the following points: socio-economic forecasting; safety and licensing; operation and maintenance; waste and decommissioning; availability and reliability. The following are the most relevant findings, conclusions and recommendations for all these aspects: Demonstrate definitively that the physical principles of nuclear fusion have been validated by means of experiments; Establish a European Industrial Group to support the demonstration phases; Create the financial and contracting framework required to construct these installations. Secure the necessary budgets for the European Union's 5th and 6th Research Programmes. Look for supplementary long term financing sources; The existing Regulatory Bodies should combine to form a single Working Group with responsibility for fusion reactor safety and licensing activities, working on the harmonisation of the regulatory processes, developing FPP safety criteria and guidelines and reviewing industry standards; To be competitive, FPPs should have high availability

  6. Nuclear Power Plant Lifetime Management Study (I)

    Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

  7. Nuclear Power Plant Lifetime Management Study (I)

    Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

  8. Power plant conceptual studies in Europe

    Maisonnier, D.; Campbell, D.; Cook, I.; Pace, L. Di; Giancarli, L.; Hayward, J.; Puma, A. Li; Medrano, M.; Norajitra, P.; Roccella, M.; Sardain, P.; Tran, M.Q.; Ward, D.

    2007-01-01

    The European fusion programme is 'reactor oriented' and it is aimed at the successive demonstration of the scientific, the technological and the economic feasibility of fusion power. The European Power Plant Conceptual Study (PPCS) has been a study of conceptual designs of five commercial fusion power plants and the main emphasis was on system integration. It focused on five power plant models which are illustrative of a wider spectrum of possibilities. They are all based on the tokamak concept and they have approximately the same net electrical power output, 1500 MWe. These span a range from relatively near-term, based on limited technology and plasma physics extrapolations, to an advanced conception. The PPCS allows one to clarify the concept of DEMO, the device that will bridge the gap between ITER and the first-of-a-kind fusion power plant. An assessment of the PPCS models with limited extrapolations highlighted a number of issues that must be addressed to establish the DEMO physics and technological basis

  9. Fusion power plant studies in Europe

    Maisonnier, D.

    2007-01-01

    The European fusion programme is reactor oriented and it is aimed at the successive demonstration of the scientific, the technological and the economic feasibility of fusion power. For a reactor-oriented fusion development programme, it is essential to have a clear idea of the ultimate goal of the programme, namely a series of models of fusion power plants, in order to define the correct strategy and to assess the pertinence of the on-going activities. The European Power Plant Conceptual Study (PPCS) has been a study of conceptual designs for commercial fusion power plants. It focused on five power plant models, named PPCS A, B, AB, C and D, which are illustrative of a wider spectrum of possibilities. They are all based on the tokamak concept and they have approximately the same net electrical power output, 1500 MWe. These span a range from relatively near-term, based on limited technology and plasma physics extrapolations, to an advanced conception. All five PPCS plant models differ substantially from the models that formed the basis of earlier European studies. They also differ from one another, which lead to differences in economic performance and in the details of safety and environmental impacts. The main emphasis of the PPCS was on system integration. Systems analyses were used to produce self-consistent plant parameter sets with approximately optimal economic characteristics for all models. In the PPCS models, the favourable, inherent, features of fusion have been exploited to provide substantial safety and environmental advantages. The broad features of the safety and environmental conclusions of previous studies have been confirmed and demonstrated with increased confidence. The PPCS study highlighted the need for specific design and R and D activities, in addition to those already underway within the European long term R and D programme, as well as the need to clarify the concept of DEMO, the device that will bridge the gap between ITER and the first

  10. Power-plant-related estuarine zooplankton studies

    Sage, L.E.; Olson, M.M.

    1981-01-01

    In-plant studies examining the effects of entrainment on zooplankton and field studies examining zooplankton abundance, composition, and distribution in the Chesapeake Bay in the vicinity of Calvert Cliffs Nuclear Power Plant have been conducted from 1974 to the present. The evolution of these studies, with particular emphasis on design and statistical treatment, is discussed. Entrainment study designs evolved from discrete sampling episodes at 4-h intervals over 24 h to a time-series sampling design in which sampling took place every 30 min over 24 and 48-h periods. The near-field study design and samping methods have included replicated net tows, using 0.5-m nets, and replicated and nonreplicated pumped sampling, using a high-speed centrifugal pump. 16 refs

  11. Plant life management study of Japanese nuclear power plants

    Fukuda, Toshihiko

    1999-01-01

    Already more than twenty-five years have passed since the first commercial LWR plant went into operation in Japan. In this situation, MITI and 3 electric utilities (Tokyo Electric Power Company, Kansai Electric Power Co., Inc, Japan Atomic Power Company) have started a plant life management (PLM) study from 1994 to evaluate the long-term integrity of major systems, structures and components of aged LWR plants and ensure the safe, steady and highly reliable long-term operation. It consists of two phases: part 1 study and part 2 study. The part 1 study started in 1994 and focused on seven typical safety-related components. The part 1 study reports were made public in 1996. The part 2 study started in 1997. In this study we reviewed not only safety-related components but also plant reliability related components. The part 2 study reports were opened to the public in February 1999. This paper shows a summary of the part 2 study and our future PLM program. (author)

  12. The German nuclear power plant safety study

    1979-01-01

    With this study a new approach has been chosen, taking nuclear power plants as an example to assess and to describe the risks arising from the use of modern technology, including those hazards emanating from the rather hypothetical possibility of occurrence of very serious accidents. Following the definition of basic concepts and methods to be applied in risk assessment studied, as well as a brief account of the design and operating mode of nuclear power plants with PWRs', accidents and failures to be considered in a safety study are described. Using the course-of-event and fault tree analysis, the probability of fission product release as a consequence of failures in safety systems or of core meltdown is evaluated. Subsequently, the theoretical model for assessment of reactor accident consequences is presented, discussing such aspects as the dispersion of radioactivity in the atmosphere, the radiation dose model, safety and countermeasures, the model for the evaluation of health hazards as well as methods and calculations for estimating the reliability of risk assessments together with the remaining uncertainties. In an appendix to this study, the analyses presented in the study are discussed in the light of the TMI-2 event. This safety study showing the possibilities of detecting, keeping in check and minimizing harmful effects, can be regarded as a contribution to a better understanding of our modern, highly industrialised society, and eventually to an improvement of the quality of life. (GL) 891 GL/GL 892 MB [de

  13. Studies on carbon dioxide power plant, (3)

    Akagawa, Koji; Fujii, Terushige; Sakaguchi, Tadashi; Kawabata, Yasusuke; Kuroda, Toshihiro.

    1980-01-01

    A power generating plant using carbon dioxide instead of water has been studied by the authors, as high efficiency can be obtained in high temperature range (higher than 650 deg C) and turbines become compact as compared with the Rankine steam cycle. In this paper, the theoretical analysis of the dynamic characteristics of this small power generating plant of supercritical pressure and the comparison with the experimental results are reported. In the theoretical analysis, the linear approximation method using small variation method was adopted for solution. Every component was modeled as the concentrated constant system, and the transfer function for each component was determined, then simulation was carried out for the total system synthesizing these components. The approximation of physical values, and the analysis of a plunger pump, a regenerator, a heater, a vapor valve, a turbine and a blower, piping, and pressure drop are described. The response to the stepwise changes of heating, flow rate, opening of a vapor valve and a load control valve for a blower was investigated. The theoretical anaysis and the experimental results were in good agreement, and this analysis is applicable to the carbon dioxide plant of practical scale. (Kako, I.)

  14. Demonstration tokamak-power-plant study (DEMO)

    1982-09-01

    A study of a Demonstration Tokamak Power Plant (DEMO) has been completed. The study's objective was to develop a conceptual design of a prototype reactor which would precede commercial units. Emphasis has been placed on defining and analyzing key design issues and R and D needs in five areas: noninductive current drivers, impurity control systems, tritium breeding blankets, radiation shielding, and reactor configuration and maintenance features. The noninductive current drive analysis surveyed a wide range of candidates and selected relativistic electron beams for the reference reactor. The impurity control analysis considered both a single-null poloidal divertor and a pumped limiter. A pumped limiter located at the outer midplane was selected for the reference design because of greater engineering simplicity. The blanket design activity focused on two concepts: a Li 2 O solid breeder with high pressure water cooling and a lead-rich Li-Pb eutectic liquid metal breeder (17Li-83Pb). The reference blanket concept is the Li 2 O option with a PCA structural material. The first wall concept is a beryllium-clad corrugated panel design. The radiation shielding effort concentrated on reducing the cost of bulk and penetration shielding; the relatively low-cost outborad shield is composed of concrete, B 4 C, lead, and FE 1422 structural material

  15. Optical study of solar tower power plants

    Eddhibi, F; Amara, M Ben; Balghouthi, M; Guizani, A

    2015-01-01

    The central receiver technology for electricity generation consists of concentrating solar radiation coming from the solar tracker field into a central receiver surface located on the top of the tower. The heliostat field is constituted of a big number of reflective mirrors; each heliostat tracks the sun individually and reflects the sunlight to a focal point. Therefore, the heliostat should be positioned with high precision in order to minimize optical losses. In the current work, a mathematical model for the analysis of the optical efficiency of solar tower field power plant is proposed. The impact of the different factors which influence the optical efficiency is analyzed. These parameters are mainly, the shading and blocking losses, the cosine effect, the atmospheric attenuation and the spillage losses. A new method for the calculation of blocking and shadowing efficiency is introduced and validated by open literature

  16. German risk study 'nuclear power plants, phase B'

    Heuser, F.W.

    1989-01-01

    The results of the German risk study 'Nuclear power plants, phase B' indicate that an accident in a nuclear power plant which cannot be managed by the safety systems according to design, is extremely improbable: Its probability is at about 3 to 100,000 per year and plant. Even if the safety systems fail, emergency measures can be effected in a nuclear power plant to prevent an accident. These in-plant emergency measures diminish the probability of a core meltdown to about 4 to 1,000,000 per year and plant. Hence, the accident risk is greatly reduced. The information given by the author are to smooth the emotional edge in the discussion about the safety of nuclear power plants. (orig.) [de

  17. The German risk study for nuclear power plants

    Birkhofer, A.

    1980-01-01

    In August 1979 results of the ''German Risk Study for Nuclear Power Plants'' were published. The Main Report, in which approach and results of the study are documented, has been available since the end of 1979. It was the charter of the study - which was performed on behalf of the Minister of Research and Technology of the Federal Republic of Germany - to apply as far as possible the methods of the US Reactor Safety Study (WASH-1400) to German plant and site conditions. A direct transfer of the results was not deemed justified, mainly for the following reasons: There is quite a number of differences between the design of the reference plants of WASH-1400 (Surry-1, Peach Bottom-2) and German nuclear power plants. The mean population density in the Federal Republic of Germany is more than ten times of the United States. In the vicinity of nuclear power plants the ratio is about 3:1. To calculate the collective risk resulting from reactor accidents, a total of 25 plants at 19 different sites in the Federal Republic of Germany were considered. This included all plants with 600 MW or more electrical output, which were in operation, under construction or in licensing process by July 1, 1977. As an approximation to the real situation, it has been assumed that all 25 plants are technically identical to the reference plant

  18. Study of nuclear power plant stability. Trip criteria

    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)

  19. Optimizing the Utility Power of a Geothermal Power Plant using Variable Frequency Drive (VFD) (Case Study: Sibayak Geothermal Power Plant)

    Sinaga, R. H. M.; Manik, Y.

    2018-03-01

    Sibayak Geothermal Power Plant (SGPP) is one of the plants being developed by Pertamina Geothermal Energy (PGE) at the upstream phase. At the downstream phase, State - owned Electricity Company (PLN) through PT. Dizamatra Powerindo is the developer. The gross capacity of the power plant is 13.3 MW, consisting 1 unit of Monoblock (2 MW) developed by PGE and 2 units (2×5.65 MW) operated through Energy Sales Contract by PLN. During the development phase of a geothermal power plant, there is a chance to reduce the utility power in order to increase the overall plant efficiency. Reducing the utility power can be attempted by utilizing the wet bulb temperature fluctuation. In this study, a modeling process is developed by using Engineering Equation Solver (EES) software version 9.430. The possibility of energy saving is indicated by condenser pressure changes as a result of wet bulb temperature fluctuation. The result of this study indicates that the change of condenser pressure is about 50.8% on the constant liquid/gas (L/G) condition of the wet bulb temperature of 15°C to 25°C. Further result indicates that in this power plant, Cooling Tower Fan (CTF) is the facility that has the greatest utility load, followed by Hot Well Pump (HWP). The saving of the greatest utility load is applied trough Variable Frequency Drive (VFD) instrumentation. The result of this modeling has been validated by actual operations data (log sheet). The developed model has also been reviewed trough Specific Steam Consumption (SSC), resulting that constant L/G condition allows the optimum condition on of the wet bulb temperature of 15°C to 25°C.

  20. Siting studies for new nuclear power plants in Argentina

    Barbaran, Gustavo A.

    2008-01-01

    This paper is a summary of the thesis prepared by the Group of Prospective and Energy Planning of the National Atomic Energy Commission for the 'Specialization on Applications of Nuclear Technology Course' of the Instituto Balseiro in 2007. It describes the evolution of siting studies through time and the main focus worldwide in this type of studies. Then, it makes a brief review of previous siting studies of nuclear power plants conducted in Argentina. It carries out a description of the methodology to conduct a site evaluation for nuclear power plants according to actual international criteria. Finally, it describes the licensing process that follows every site study. (author) [es

  1. DEMO and fusion power plant conceptual studies in Europe

    Maisonnier, David; Cook, Iau; Pierre, Sardain; Lorenzo, Boccaccini; Luigi, Di Pace; Luciano, Giancarli; Prachai, Norajitra; Aldo, Pizzuto

    2006-01-01

    Within the European Power Plant Conceptual Study (PPCS) four fusion power plant 'models' have been developed. Two of these models were developed considering limited extrapolations both in physics and in technology. For the two other models, advanced physics scenarios have been identified and combined with advanced blanket concepts that allow higher thermodynamic efficiencies of the power conversion systems. For all the PPCS models, systems analyses were used to integrate the plasma physics and technology constraints to produce self-consistent plant parameter sets. The broad features of the conclusions of previous studies on safety, environmental impact and economics have been confirmed for the new models and demonstrated with increased confidence. The PPCS also helps in the definition of the objectives and in the identification of the design drivers of DEMO, i.e. the device between the next step (ITER) and a first-of-a-kind reactor. These will constitute the basis of the European DEMO Conceptual Study that has recently started

  2. Feasibility study on rehabilitation of ICE San Antonio Power Plant

    NONE

    2001-03-01

    Costa Rica takes a power generation system using hydro power generation as the main source, and possesses medium-capacity gas turbines to supplement needs in the dry season and the peak load. However, a problem has come up that, in addition to the cost rise in gas turbine fuel, the power generation efficiency has been aggravating due to aged deterioration of the generators being used. In association therewith, the problem is now a factor to increase CO2 emission, which is a worldwide problem. Keeping in mind to link it to the clean development mechanism (CDM), the present project is, taking up the SAN ANTONIO power plant as the investigation object, intended to perform a comprehensive discussion on the CO2 emission reducing effect, profitability, and proliferation effect, by executing the conceptual plant design. The up-grading plan for thermal power generation systems in Costa Rica consists of replacement of the gas turbines, handling of phase modifiers, and achievement of the combined cycle. The plan agrees with the present feasibility study intended of CO2 emission reduction, consisting of the modification plan of the SAN ANTONIO power plant, that is the plan to replace the over-aged gas turbines at the power plant. Its necessity has been identified. It was disclosed that the project has the effects of reducing CO2 of 82,000 tons annually, and the investment can be recovered in nine years. (NEDO)

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

    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....

  4. Geothermal power plants principles, applications, case studies and environmental impact

    DiPippo, Ronald

    2008-01-01

    Ron DiPippo, Professor Emeritus at the University of Massachusetts Dartmouth, is a world-regarded geothermal expert. This single resource covers all aspects of the utilization of geothermal energy for power generation from fundamental scientific and engineering principles. The thermodynamic basis for the design of geothermal power plants is at the heart of the book and readers are clearly guided on the process of designing and analysing the key types of geothermal energy conversion systems. Its practical emphasis is enhanced by the use of case studies from real plants that increase the reader'

  5. Reactor safety study applied to the Forsmark 3 Power Plant

    Ericsson, G.; Tiren, L.I.

    1978-01-01

    A reactor safety study of the Forsmark 3 BWR power plant has been carried out for the purpose of calculating core melt probabilities using WASH-1400 methods. A sensitivity analysis shows that the calculated core melt probability is changed by approximately a factor of 10 depending on assumptions made with respect to the probability of human error. The importance of the availability of off-site power and the influence of common cause failure is also discussed. (author)

  6. Thermoeconomic studies applied to maintenance of power plants

    Carvalho, F.R.; Horta Nogueira, L.A.

    1996-01-01

    The thermoeconomic method is an important tool aiming to improve maintenance activities in steam power plants, becoming possible to share the irreversibilities costs to each equipment, as boilers, turbines and heat exchangers. Furthermore, the effects related to changes in operational and design parameters can be studied in a detailed way, evaluating the local and distributed effects. In this work, after a brief review of power plant maintenance costs concepts and values, one address a methodology for maintenance costs estimation and develops a case study of thermoeconomics of a hypothetical plant, presenting the exergy flows, exergy losses and maintenance costs distribution. Also is presented an evaluation of exergoeconomic maintenance cost, evaluating their significance, at equipment level, related to overall maintenance cost, aiming to help the maintenance activities planning. 10 refs, 3 figs, 12 tabs

  7. Implications of fusion power plant studies for materials requirements

    Cook, Ian; Ward, David; Dudarev, Sergei

    2002-01-01

    This paper addresses the key requirements for fusion materials, as these have emerged from studies of commercial fusion power plants. The objective of the international fusion programme is the creation of power stations that will have very attractive safety and environmental features and viable economics. Fusion power plant studies have shown that these objectives may be achieved without requiring extreme advances in materials. But it is required that existing candidate materials perform at least as well as envisaged in the environment of fusion neutrons, heat fluxes and particle fluxes. The development of advanced materials would bring further benefits. The work required entails the investigation of many intellectually exciting physics issues of great scientific interest, and of wider application than fusion. In addition to giving an overview, selected aspects of the science, of particular physics interest, are illustrated

  8. Nuclear power plant diagnostics study at the Midland training simulator

    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

  9. Interdisciplinary Study of Numerical Methods and Power Plants Engineering

    Ioana OPRIS

    2014-08-01

    Full Text Available The development of technology, electronics and computing opened the way for a cross-disciplinary research that brings benefits by combining the achievements of different fields. To prepare the students for their future interdisciplinary approach,aninterdisciplinary teaching is adopted. This ensures their progress in knowledge, understanding and ability to navigate through different fields. Aiming these results, the Universities introduce new interdisciplinary courses which explore complex problems by studying subjects from different domains. The paper presents a problem encountered in designingpower plants. The method of solvingthe problem isused to explain the numerical methods and to exercise programming.The goal of understanding a numerical algorithm that solves a linear system of equations is achieved by using the knowledge of heat transfer to design the regenerative circuit of a thermal power plant. In this way, the outcomes from the prior courses (mathematics and physics are used to explain a new subject (numerical methods and to advance future ones (power plants.

  10. Study of CO2 capture processes in power plants

    Amann, J.M.

    2007-12-01

    The aim of the present study is to assess and compare various processes aiming at recover CO 2 from power plants fed with natural gas (NGCC) and pulverized coal (PC). These processes are post-combustion CO 2 capture using chemical solvents, natural gas reforming for pre-combustion capture by methanol and oxy-fuel combustion with cryogenic recovery of CO 2 . These processes were evaluated using the process software Aspen PlusTM to give some clues for choosing the best option for each type of power plant. With regard to post-combustion, an aqueous solution based on a mixture of amines (N-methyldiethanolamine (MDEA) and triethylene tetramine (TETA)) was developed. Measurements of absorption were carried out between 298 and 333 K in a Lewis cell. CO 2 partial pressure at equilibrium, characteristic of the CO 2 solubility in the solvent, was determined up to 393 K. The solvent performances were compared with respect to more conventional solvents such as MDEA and monoethanolamine (MEA). For oxy-fuel combustion, a recovery process, based on a cryogenic separation of the components of the flue gas, was developed and applied to power plants. The study showed that O 2 purity acts on the CO 2 concentration in the flue gas and thus on the performances of the recovery process. The last option is natural gas reforming with CO 2 pre-combustion capture. Several configurations were assessed: air reforming and oxygen reforming, reforming pressure and dilution of the synthesis gas. The comparison of these various concepts suggests that, in the short and medium term, chemical absorption is the most interesting process for NGCC power plants. For CP power plants, oxy-combustion can be a very interesting option, as well as post-combustion capture by chemical solvents. (author)

  11. Study Of Severe Accident Phenomena In Nuclear Power Plant

    Sugiyanto; Antariksawan; Anhar, R.; Arifal

    2001-01-01

    Several phenomena that occurred in the light water reactor type of nuclear power plant during severe accident were studied. The study was carried out based on the results of severe accident researches in various countries. In general, severe accident phenomena can be classified into in-vessel phenomena, retention in the reactor coolant system, and ex-vessel phenomena. In-vessel retention has been recommended as a severe accident management strategy

  12. A study on expert system applications for nuclear power plant

    Huh, Young Hwan; Kim, Yeong Jin; Park, Nam Seog; Dong, In Sook; Choi, In Seon

    1987-12-01

    The application of artificial intelligence techniques to nuclear power plants such as expert systems is rapidly emerging. expert systems can contribute significantly to the availability and the improved operation and safety of nuclear power plants. The objective of the project is to develop an expert system in a selected application area in the nuclear power plants. This project will last for 3 years. The first year's tasks are: - Information collection and literature survey on expert systems. - Analysis of several applicable areas for applying AI technologies to the nuclear power plants. - Conceptual design of a few selected domains. - Selection of hardware and software tools for the development of the expert system

  13. Study on Economic Evaluation of Nuclear Power Plant's SSC

    Yun, Eun-Sub; Park, Young-Sheop

    2007-01-01

    As the operating year of nuclear power plant increases, more improvement plans on degraded SSCs(Structure, System, and Component) are suggested. Because of safety concern, the maintenance and replacing cost of nuclear power plant's SSCs are usually high and it can be a burden to financial control. To satisfy both safety and economic problems, systematic and efficient plans are needed. For this reason, KHNP is now developing the LTAM (Long Term Asset Management) program to establish the long term improvement plans for SSCs, from safety and economic point of views. Actually LTAM program is one of the steps of INPO ER (Equipment Reliability) process. In USA, EPRI (Electric Power Research Institute) has developed the LCM (Life Cycle Management) program and it was applied to some nuclear power plants. In this program, several alternatives are candidated. Then, economic evaluation is applied to each alternative. The result of economic evaluation affects to the final alternative decision. In this study, EPRI's economic evaluation method is reviewed

  14. Studies on human factors in nuclear power plants

    Tsukuda, H.; Miyaoka, S.

    1988-01-01

    In order to raise the reliability and safety of nuclear power plants to the highest possible level, improvements to the mechanical system alone are not sufficient. Human factors must be systematically analysed and the causes and mechanisms of human error clarified to allow the development of countermeasures that will reduce error as much as possible. The paper introduces research in two areas, fundamental clarification of human behavioural, physiological and psychological characteristics to aid in the development of preventive measures for reducing error, and studies involving analysis of actual cases of accidents and failures related to man along with development of countermeasures to prevent the recurrence of such cases. The paper especially considers the latter area. The Human Performance Evaluation System (HPES) developed by the Institute of Nuclear Power Operations (INPO) in the USA was applied on a trial basis to 31 recent accidents and failures at Japanese nuclear power plants. The effectiveness of and possible improvement to HPES were considered. Also, cases that were not directly linked to accidents or failures were analysed using a method developed independently in Japan using data collected from a survey of approximately 3,000 power plant personnel. Fundamental research on human behaviour, physiology and psychology are also introduced. (author). 4 figs

  15. Review of avian mortality studies at concentrating solar power plants

    Ho, Clifford K.

    2016-05-01

    This paper reviews past and current avian mortality studies at concentrating solar power (CSP) plants and facilities including Solar One in California, the Solar Energy Development Center in Israel, Ivanpah Solar Electric Generating System in California, Crescent Dunes in Nevada, and Gemasolar in Spain. Findings indicate that the leading causes of bird deaths at CSP plants are from collisions (primarily with reflective surfaces; i.e., heliostats) and singeing caused by concentrated solar flux. Safe irradiance levels for birds have been reported to range between 4 and 50 kW/m2. Above these levels, singeing and irreversible damage to the feathers can occur. Despite observations of large numbers of "streamers" in concentrated flux regions and reports that suggest these streamers indicate complete vaporization of birds, analyses in this paper show that complete vaporization of birds is highly improbable, and the observed streamers are likely due to insects flying into the concentrated flux. The levelized avian mortality rate during the first year of operation at Ivanpah was estimated to be 0.7 - 3.5 fatalities per GWh, which is less than the levelized avian mortality reported for fossil fuel plants but greater than that for nuclear and wind power plants. Mitigation measures include acoustic, visual, tactile, and chemosensory deterrents to keep birds away from the plant, and heliostat aiming strategies that reduce the solar flux during standby.

  16. Feasibility study on modernization of North Bangkok Thermal Power Plant

    NONE

    2001-03-01

    With an objective to save energies and reduce global warming gas emission, a feasibility study was performed on the oil burning thermal power plant in the city of North Bangkok in Thailand to reconstruct the plant into a natural gas burning combined cycle power plant. In the project, the old facilities with an output of 237.8 MW using three steam turbines in total will be reconstructed into a plant comprising of two steam turbines for 256,2 MW and two gas turbines for 460.4 MW, or a facility of 716.6 MW in total. The plant construction will have the gas turbines, steam turbines, generators, and a waste heat recovered steam generator fixed on one axis, two of which will be installed. The gas turbines will use natural gas as fuel, and the steam turbines will be operated by steam from the waste heat recovered steam generator. As a result of the discussions, the reduction of the energy consumption for a period of 40 years will correspond to crude oil of 20,560 kt, while the reduction of the global warming gas emission will be 107,200 t-CO2. In addition, the energy saving cost will be 9-ton crude oil equivalent/one million yen, and the cost for reduction of the global warming gas emission will be 47 t-CO2/one million yen. (NEDO)

  17. Cooling problems of thermal power plants. Physical model studies

    Neale, L.C.

    1975-01-01

    The Alden Research Laboratories of Worcester Polytechnic Institute has for many years conducted physical model studies, which are normally classified as river or structural hydraulic studies. Since 1952 one aspect of these studies has involved the heated discharge from steam power plants. The early studies on such problems concentrated on improving the thermal efficiency of the system. This was accomplished by minimizing recirculation and by assuring full use of available cold water supplies. With the growing awareness of the impact of thermal power generation on the environment attention has been redirected to reducing the effect of heated discharges on the biology of the receiving body of water. More specifically the efforts of designers and operators of power plants are aimed at meeting or complying with standards established by various governmental agencies. Thus the studies involve developing means of minimizing surface temperatures at an outfall or establishing a local area of higher temperature with limits specified in terms of areas or distances. The physical models used for these studies have varied widely in scope, size, and operating features. These models have covered large areas with both distorted geometric scales and uniform dimensions. Instrumentations has also varied from simple mercury thermometers to computer control and processing of hundreds of thermocouple indicators

  18. Feasibility study on rehabilitation of KESC gas turbine power plant

    NONE

    2001-03-01

    As to power generation facilities of Karachi Electric Power Supply Corporation in Karachi (KESC), the Islamic Republic of Pakistan, feasibility study on the rehabilitation was conducted in consideration of the CDM (clean development mechanism) project. In Pakistan, 13 gas turbine power plants started operation at the same time as the time when the power plant studied this time started operation, and therefore it is predicted that they also have the same troubles caused by the aged deterioration. As the rehabilitation project, two cases were proposed: In Case 1, gas turbine and generator are both exchanged, and in Case 2, gas turbine is only exchanged, and generator is reused after repair. The work term is approximately 9 months in both cases. The initial investment is $84 million in Case 1 and $78 million in Case 2. The energy conservation effect per cost is 107 t/y/million yen and 101 t/y/million yen, respectively. Further, the amount of greenhouse effect gas reduction per cost is 330 t-CO2/y/million yen and 313 t-CO2/y/million yen, respectively. The effect of profits can be obtained after the depreciation period since the fuel price is reduced approximately 0.5%. (NEDO)

  19. Study on corrosion of thermal power plant condenser tubes

    Mohammadi, Abdolreza Rashidi; Zhaam, Ali Akbar [Niroo Research Institute, end of Poonak Bakhtari blvd., Shahrak Ghods, Tehran (Iran)

    2004-07-01

    The aim of this investigation is to study kinds of corrosion mechanisms in thermal power plant condenser tubes. Condenser is a shell and tube heat exchanger in which cooling water flows through its tubes. While the steam from low pressure turbine passes within condenser tubes, it is condensed by cooling water. The exhausted steam from low pressure turbine is condensed on external surface of condenser tubes and heat is transferred to cooling water which flow into tubes. Tubes composition is usually copper-based alloys, stainless steel or titanium. Annual damages due to corrosion cause much cost for replacement and repairing metallic equipment and installations in electric power industry. Because of existence of different contaminants in water and steam cycle, condenser tubes surfaces are exposed to corrosion. Contaminants like oxygen, carbon dioxide, chloride ion and ammonia in water and steam cycle originate several damages such as pitting and crevice corrosion, erosion, galvanic attack, SCC, condensed corrosion, de-alloying in thermal power plant condenser. The paper first states how corrosion damage takes place in condensers and then introduces types of usual alloys used in condensers and also their corrosion behavior. In continuation, a brief explanation is presented about kinds of condenser failures due to corrosion. Then, causes and locations of different mechanisms of corrosion events on condenser tubes and effects of different parameters such as composition, temperature, chloride and sulfide ion concentration, pH, water velocity and biological precipitation are examined and finally protection methods are indicated. Also some photos of tubes specimens related to power plants are studied and described in each case of mentioned mechanisms. (authors)

  20. Geothermal power plants principles, applications, case studies and environmental impact

    DiPippo, Ronald

    2012-01-01

    Now in its 3e, this single resource covers all aspects of the utilization of geothermal energy for power generation using fundamental scientific and engineering principles. Its practical emphasis is enhanced by the use of case studies from real plants that increase the reader's understanding of geothermal energy conversion and provide a unique compilation of hard-to-obtain data and experience. Important new chapters cover Hot Dry Rock, Enhanced Geothermal Systems, and Deep Hydrothermal Systems. New, international case studies provide practical, hands-on knowledge.

  1. French studies on the thermal effluents of electric power plants

    Dezes-Cadiere, H.

    1976-01-01

    This report presents a synthesis of studies made in France in the thermal effluent field: thermal power plant cooling systems, transfer and dispersion of thermal effluents in the receptive media, effects of thermal effluents on water physicochemistry and biochemistry, effects of thermal effluents on aquatic ecosystems, and, possibilities of waste heat recovery with the view of utilization in agriculture, aquaculture and district heating. A catalogue of French organizations working or having data on thermal effluents is presented, as also an alphabetical list of the contacted persons. A bibliography of French documents concerning the previously mentioned studies is finally given (193 refs.) [fr

  2. Parametric study of prospective early commercial OCMHD power plants /PSPEC/

    Marston, C. H.; Bender, D. J.; Hnat, J. G.; Dellinger, T. C.

    1980-06-01

    The paper presents a parametric study conducted to obtain the performance, economics, natural resource requirements, and environmental impact of moderate technology MHD/steam power plants that do not require development of direct-fired high-temperature air heaters. The study was divided into three base cases, each with a reference case and parametric variations. The case using recuperative air preheat in the range of 1000 F to 1300 F, combined with O2 enrichment to 42% by volume has been selected for conceptual design.

  3. ELMO Bumpy Torus Reactor and power plant: conceptual design study

    Bathke, C.G.; Dudziak, D.J.; Krakowski, R.A.

    1981-08-01

    A complete power plant design of a 1200-MWe ELMO Bumpy Torus Reactor (EBTR) is presented. An emphasis is placed on those features that are unique to the EBT confinement concept, with subsystems and balance-of-plant items that are more generic to magnetic fusion being adapted from past, more extensive tokamak reactor designs. Similar to the latter tokamak studies, this conceptual EBTR design also emphasizes the use of conventional or near state-of-the-art engineering technology and materials. An emphasis is also placed on system accessibility, reliability, and maintainability, as these crucial and desirable characteristics relate to the unique high-aspect-ratio configuration of EBTs. Equal and strong emphasis is given to physics, engineering/technology, and costing/economics components of this design effort. Parametric optimizations and sensitivity studies, using cost-of-electricity as an object function, are reported. Based on these results, the direction for future improvement on an already attractive reactor design is identified

  4. A study on economic power dispatch grid connected PV power plant in educational institutes

    Singh, Kuldip; Kumar, M. Narendra; Mishra, Satyasis

    2018-04-01

    India has main concerns on environment and escalation of fuel prices with respect to diminution of fossil fuel reserves and the major focus on renewable Energy sources for power generation to fulfill the present and future energy demand. Installation of PV power plants in the Educational Institutions has grown up drastically throughout India. More PV power plant are integrated with load and grid through net metering. Therefore, this paper is an analysis of the 75kWp PV plant at chosen buses, considering the need of minimum demand from the grid. The case study is carried out for different generation level throughout the day and year w.r.t load and climate changes, load sharing on grid. The economic dispatch model developed for PV plant integrated with Grid.

  5. Nuclear power plant site selection: a case study

    Lugasi, Y.; Mehrez, A.; Sinuany-Stern, Z.

    1985-01-01

    Selecting the site for a nuclear power plant involves the evaluation of numerous criteria and the professional judgment of various experts. The Israel Atomic Energy Commission has been concerned with the problem of selecting a site for a nuclear power station. Previous studies have been performed by the commission to identify potential sites. There were initial screenings where potential sites were chosen according to various minimal criteria and international standards. Only sites that met all the criteria were chosen. A study was made to find the most preferred site among the potential sites that met all the criteria. Two mathematical approaches were used: Keeney's multiattribute utility function and Saaty's eigenvalue prioritization technique. Both models ranked the same site as the most desirable; however, the models differed in their ranking of the other sites

  6. STARFIRE: a commercial tokamak fusion power plant study

    1980-09-01

    STARFIRE is a 1200 MWe central station fusion electric power plant that utilizes a deuterium-tritium fueled tokamak reactor as a heat source. Emphasis has been placed on developing design features which will provide for simpler assembly and maintenance, and improved safety and environmental characteristics. The major features of STARFIRE include a steady-state operating mode based on continuous rf lower-hybrid current drive and auxiliary heating, solid tritium breeder material, pressurized water cooling, limiter/vacuum system for impurity control and exhaust, high tritium burnup and low vulnerable tritium inventories, superconducting EF coils outside the superconducting TF coils, fully remote maintenance, and a low-activation shield. A comprehensive conceptual design has been developed including reactor features, support facilities and a complete balance of plant. A construction schedule and cost estimate are presented, as well as study conclusions and recommendations.

  7. STARFIRE: a commercial tokamak fusion power plant study

    1980-09-01

    STARFIRE is a 1200 MWe central station fusion electric power plant that utilizes a deuterium-tritium fueled tokamak reactor as a heat source. Emphasis has been placed on developing design features which will provide for simpler assembly and maintenance, and improved safety and environmental characteristics. The major features of STARFIRE include a steady-state operating mode based on continuous rf lower-hybrid current drive and auxiliary heating, solid tritium breeder material, pressurized water cooling, limiter/vacuum system for impurity control and exhaust, high tritium burnup and low vulnerable tritium inventories, superconducting EF coils outside the superconducting TF coils, fully remote maintenance, and a low-activation shield. A comprehensive conceptual design has been developed including reactor features, support facilities and a complete balance of plant. A construction schedule and cost estimate are presented, as well as study conclusions and recommendations

  8. Feasibility study for Tashkent Heat and Power Plant Modernizing Project

    NONE

    2001-03-01

    An investigational study was carried out of the project for energy conservation and greenhouse effect gas emission reduction by introducing the newest and most powerful gas turbine cogeneration facilities to the Tashkent cogeneration plant in Uzbekistan. At the Tashkent cogeneration plant, each of the facilities is being superannuated, which leads to lowering of operational reliability and increase in cost of repairs. In the project, studied was the introduction of the newest and most powerful gas turbine cogeneration facilities with heat output of 100 Gcal/h equivalent to that of one can of the existing hot water boiler and with generated output of 80MW. As a result of the study, obtained were the energy conservation amount of 83.9 ktoe/y and the greenhouse effect gas reduction amount of 179.7 kt-CO2/y. The initial investment amount was 10.003 billion yen. Expenses vs. effects were 8.39 toe/y-million yen in energy conservation amount and 18.0 t-CO2/y-million yen in greenhouse effect gas reduction amount. In the study of profitability, the internal earning rate was 9.24% after tax, the return yield of capital was 41.26%, and the period of ROI was 16.9 years. (NEDO)

  9. Cooling water in the study of nuclear power plants sites

    Martinez, J.J.C.

    1990-01-01

    The location of an electric power plant has its limitations as regards the availability of apt sites. The radiosanitary risk, seismic risk and the overload capacity of the ground can be generically enumerated, being the cooling water availability for an electric power plant a basic requirement. Diverse cooling systems may be employed but the aim must always be that thermal contamination in the immediate environment be the least possible. (Author) [es

  10. STARFIRE: a commercial tokamak fusion power plant study

    1980-09-01

    This volume contains chapters on each of the following topics: (1) radioactivity, (2) heat transport and energy conversion, (3) tritium systems, (4) electrical storage and power supplies, (5) support structure, (6) cryogenics, (7) instrumentation and control, (8) maintenance and operation, (9) balance of plant design, (10) safety and environmental analysis, (11) economic analysis, and (12) plant construction.

  11. STARFIRE: a commercial tokamak fusion power plant study

    1980-09-01

    This volume contains chapters on each of the following topics: (1) radioactivity, (2) heat transport and energy conversion, (3) tritium systems, (4) electrical storage and power supplies, (5) support structure, (6) cryogenics, (7) instrumentation and control, (8) maintenance and operation, (9) balance of plant design, (10) safety and environmental analysis, (11) economic analysis, and (12) plant construction

  12. Case study of siting technology for underground nuclear power plant

    Hibino, Satoshi; Komada, Hiroya; Honsho, Shizumitsu; Fujiwara, Yoshikazu; Motojima, Mutsumi; Nakagawa, Kameichiro; Nosaki, Takashi

    1991-01-01

    Underground siting method is one of new feasible siting methods for nuclear power plants. This report presents the results on case studies on underground siting. Two sites of a steeply inclined and plateau like configurations were selected. 'Tunnel type cavern; all underground siting' method was applied for the steeply inclined configuration, and 'shaft type semi-cavern; partial underground siting' method was applied for the plateau like configuration. The following designs were carried out for these two sites as case studies; (1) conceptual designs, (2) geological surveys and rock mechanics tests, (3) stability analysis during cavern excavations, (4) seismic stability analysis of caverns during earthquake, (5) reinforcement designs for caverns, (6) drainage designs. The case studies showed that these two cases were fully feasible, and comparison between two cases revealed that the 'shaft type semi-cavern; partial underground siting' method was more suitable for Japanese islands. As a first step of underground siting, therefore, the authors recommend to construct a nuclear power plant by this method. (author)

  13. Studies on environment safety and application of advanced reactor for inland nuclear power plants

    Wei, L.; Jie, L.

    2014-01-01

    To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

  14. Fire safety study of Dodewaard and Borssele nuclear power plants

    1988-03-01

    From the nuclear and conventional fire safety audits of both Dutch nuclear power plants performed under supervision of the Nuclear Safety Inspectorate and the Inspectorate for the Fire Services it turns out that the fire safety is sufficient however amenable for improvement. Besides a detailed description of the method of examination, the study 'Fire Safety' contains the results of the audit and 14 respectively 15 recommendations for improvement of the fire safety in Dodewaard and Borssele. The suggested recommendations which are applicable to both power plants are the following: fire fighting training for operators and guards, a complete emergency ventilation system of the control room, increase in the number of detectors and alarms, an increase in the quantity of water available for high-pressure fire fighting, improvement of fire barriers between several redundancies of nuclear safety systems, an investigation and possible improvement of the heat and radiation protection offered by presently used fire fighting suits. For Dodewaard a closed emergency staircase in the reactor building (secondary containment) is deemed necessary for personnel emergency escape routes and continued fire fighting if required

  15. Study on alternatives of inertisation of nuclear power plant containment

    Baron, J.H.; Zarate, S.M.

    1998-01-01

    In the course of a severe accident in a nuclear power plant, the hydrogen generation and other flammable gases, during the core degradation phase and the interaction corium-concrete, could produce the failure of the containment by overpressure of by combustion. According to the analysis of the potential effects of hydrogen evolution, following accidents inside the containment trough a Defense-in depth principle, which attempts to assure that the containment must not fail catastrophically, two techniques have been evaluated: a: Inertisation pre-accident and b: Inertisation post-accident. The technique of inertisation pre-accident consists in replacing the air of the containment with inert-gas like nitrogen (N 2 ) or carbon dioxide (CO 2 ) during the normal operation. The inertisation post-accident in combination with early venting system consists in replacing the air of the containment with inert-gas like nitrogen (N 2 ) or carbon dioxide (CO 2 ), immediately after the beginning of the accident, while the radioactivity is still negligible inside the containment. A system of inertisation pre-accident with nitrogen is used on BWR Mark I and Mark II. Investigations on the inertisation post-accident of the containment atmosphere during severe accidents have been carried out with different objectives from principles of the decade of 1980. Studies concerning hydrogen problem for the nuclear power plants Atucha I and CAREM-25 have permitted to know that the hydrogen generation during an accidental sequence with core degradation, would result important, being able to arrive to form explosive mixtures. In the present work, the applicability of the techniques of inertisation is analyzed for the containment of the Atucha I and CAREM-25, considering the particular design characteristics of these plants. (author) [es

  16. Feasibility study on Bobovdol thermal power plant upgrading project

    NONE

    2001-03-01

    A survey has been made in relation with the improvement project intended of energy conservation, and reduction of global warming gas emission at the Bobovdol thermal power plant located in the suburb of Sofia, the capital of the Republic of Bulgaria. The existing Bobovdol power plant having a total capacity of 630 MW with three generators is a coal burning thermal power plant having been used already for 23 to 27 years, hence over-aged. The survey has discussed an improvement project of scrap-and-build type to make the plant a high-efficiency gas combined cycle power plant using gas turbines. The project calls for building 210-MW gas combined power generation facilities having 70-MW gas turbines, one each in three stages in 2007, 2012 and 2017. As a result of the discussions, the fuel consumption reducing rate was found to reach 37.99%, whereas the cumulative energy saving quantity in 41 years will reach 16.37 million tons of fuel oil equivalent. In addition, the reduction rate of global warming gas emission is 57.75%, and the cumulative reduction quantity in 41 years is 105.18 million tons. (NEDO)

  17. Project approach study for nuclear power plants in the Netherlands

    1985-11-01

    The new nuclear program in the Netherlands comprises the construction of two to four nuclear power plants up to the year 2000. The main objective pursued with the implementation of the nuclear program is the supply of low-cost electricity in the future. In order to prepare the program and to provide a basis for further decisions, the Ministry of Economic Affairs has entrusted Motor-Columbus Consulting Engineers Inc., Baden, Switzerland, with a study to determine the most suitable project approach option(s) for the implementation of the future nuclear program in the Netherlands. In carrying out this study, Motor-Columbus investigated the following main project approach options: 1. turnkey contract approach; 2. split-package contract approach; 3. multi-contract approach. It is concluded that if applied in the appropriate way, the normal turnkey contract approach represents the most suitable approach under the prevailing situation in the Netherlands. (orig.)

  18. Environmental study of the Wairakei Power Plant. [Effects of hydroelectric power plant on ecology of Waikato River Basin, New Zealand

    Axtmann, R C

    1974-12-01

    Physical, chemical, biological, ecological, and aesthetic aspects of the Wairakei Power Plant are examined, in varying detail, but with primary emphasis on the chemical and thermal effluents. When flows are average or higher in the Waikato River, the Plant's environmental effects are not overly severe. However, operating requirements for the Waikato Hydro-electric System are such that the Plant sporadically produces wastes that may affect the human and natural environment adversely. These adverse effects are not presently too serious, but suggestions are made for improving the Plant's overall environmental performance. Although the point is not discussed in detail, it is clear from the results of the study that any additional thermal plants on the Waikato could strain the river's absorptive capacities severely, unless alternative disposal techniques are used for the various effluents.

  19. Study on large release frequency of nuclear power plants

    Chen Yan; Song Wei; Li Chaojun; Fu Zhiwei; Wang Zhe; Zuo Jiaxu; Tong Jiejuan

    2014-01-01

    There are several definitions of large release frequency of nuclear power plant. This paper reviews the meanings of large release and requirement of large release frequency provided by IAEA, NRC and WENRA, analyses the relationship between the meanings of large release, compares the calculations of several large release frequencies, It is different frequency that the definition of LRF is not same. Last we discuss the difference between large release frequency and large early release frequency and explore the suitable definitions of LRF for nuclear power plants in China. (authors)

  20. Feasibility study on rehabilitation of MEPE gas turbine power plant

    NONE

    2001-03-01

    Myanmar generates majority of the whole electric power by using thermal power plants consisting of single gas turbines, and gas and steam composite turbines. However, because of chronic power shortage and fund unavailability, the major gas turbines are being operated in quite inadequate environment. As a result, reduction in power generation efficiency has become manifest due to aged deterioration, increasing the quantity of CO2 emission. The present project is, in order to link it to the 'Clean Development Mechanism' being carried out with developing countries, and placing Tharkayta Power Plant as the object, intended to comprehensively discuss a rehabilitation program to renew the existing gas turbines with advanced ones, in relation with feasibility of the project implementation including the effect of CO2 emission reduction, profitability, and proliferation effects. A prospect was acquired that, by replacing the gas turbines alone with 25-MW class gas turbines, the plant output will increase to 97.2 MW (78.5 MW in the existing facilities) and the plant efficiency to 43.3% (36.5% in the existing facilities). The energy saving effect during a period of 40 years would be 708,000 (toe) as heat consumption converted to crude oil, and the CO2 emission reducing effect would be 2,160,000 (t-CO2), respectively. (NEDO)

  1. Feasibility study for the partial conversion of a hydropower plant into a pumped-storage power plant: a case study of hydroelectric power plant La Barca (Asturias, Spain

    E. Antuña Yudego

    2017-01-01

    Full Text Available Renewable energy sources have reported an unprecedented increase of global installed renewable power capacity. Against the advantages provided by this renewable power generation technology it should be taken into account an important issue: these intermittent energy sources supply a fluctuating output which is difficult to manage. Pumped-storage hydro power plants reappear in these circumstances as an efficient form of energy storage which allows to use reserves when necessary, enabling power generation output to cover continuously this energy demand. The present paper shows a simplified feasibility study of the partial conversion of hydropower plant La Barca, in Asturias, into a reversible storage through the development of an algorithm to simulate its operation according to electricity market prices. For this purpose, the operation in the deviation management market is considered and the technical modifications required for the conversion are shown. The estimation of costs and incomes present a feasible scenario.

  2. Nuclear power plants

    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

  3. Seismic fragilities for nuclear power plant risk studies

    Kennedy, R.P.; Ravindra, M.K.

    1983-01-01

    Seismic fragilities of critical structures and equipment are developed as families of conditional failure frequency curves plotted against peak ground acceleration. The procedure is based on available data combined with judicious extrapolation of design information on plant structures and equipment. Representative values of fragility parameters for typical modern nuclear power plants are provided. Based on the fragility evaluation for about a dozen nuclear power plants, it is proposed that unnecessary conservatism existing in current seismic design practice could be removed by properly accounting for inelastic energy absorption capabilities of structures. The paper discusses the key contributors to seismic risk and the significance of possible correlation between component failures and potential design and construction errors

  4. Seismic PSA of nuclear power plants a case study

    Hari Prasad, M.; Dubey, P.N.; Reddy, G.R.; Saraf, R.K.; Ghosh, A.K.

    2006-07-01

    Seismic Probabilistic Safety Assessment (Seismic PSA) analysis is an external event PSA analysis. The objective of seismic PSA for the plants is to examine the existence of plant vulnerabilities against postulated earthquakes by numerically assessing the plant safety and to take appropriate measures to enhance the plant safety. Seismic PSA analysis integrates the seismic hazard analysis, seismic response analysis, seismic fragility analysis and system reliability/ accident sequence analysis. In general, the plant consists of normally operating and emergency standby systems and components. The failure during an earthquake (induced directly by excessive inertial stresses or indirectly following the failure of some other item) of an operating component will lead to a change in the state of the plant. In that case, various scenarios can follow depending on the initiating event and the status of other sub-systems. The analysis represents these possible chronological sequences by an event tree. The event trees and the associated fault trees model the sub-systems down to the level of individual components. The procedure has been applied for a typical Indian nuclear power plant. From the internal event PSA level I analysis significant contribution to the Core Damage Frequency (CDF) was found due to the Fire Water System. Hence, this system was selected to establish the procedure of seismic PSA. In this report the different elements that go into seismic PSA analysis have been discussed. Hazard curves have been developed for the site. Fragility curve for the seismically induced failure of Class IV power has been developed. The fragility curve for fire-water piping system has been generated. Event tree for Class IV power supply has been developed and the dominating accident sequences were identified. CDF has been estimated from these dominating accident sequences by convoluting hazard curves of initiating event and fragility curves of the safety systems. (author)

  5. Kansas Power Plants

    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...

  6. Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants

    Stephen Schey

    2009-07-01

    Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 – Produce Data and Analyses Task 2 – Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 – Commercial-Scale Hydrogen Production Task 4 – Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study

  7. Feasibility study of Pridneprovskaya Thermal Power Plant reconstruction project

    NONE

    2001-03-01

    With objectives of saving energy and reducing greenhouse gas emission at the Pridneprovskaya power plant in Ukraine, a scrap and build project has been discussed. This project will abolish the unit No.12 among the eight units in the existing coal burning power generation facilities, and install a natural gas burning combined cycle plant comprising of three units each with an output of 100 MW. The new plant facilities will consist of gas turbines, steam turbines, HRSG and auxiliary devices, and an air-cooled synchronous power generator with a capacity of 119 MVA. Use of natural gas as fuel reduces generation of soot, sulfur oxides, nitrogen oxides, and CO. In addition, the hot effluent and waste liquor effluent will decrease from those at the present plant. The required fund will be 30,107 million yen. The energy saving effect of this project is reduction of about 7.5 million tons of crude oil equivalent as a total in 40 years. The greenhouse effect gas will decrease by about 39 million tons as a total in 40 years. The profitability estimation calls for the number of investment recovery year of 16 years, and internal profit rate of 7.32%, wherein the implementation of the project cannot be expected as a project to be carried out by private funds. (NEDO)

  8. Development of techniques for electrochemical studies in power plant environments

    Maekelae, K.

    2000-01-01

    The properties of the oxide films on the engineering alloys used as construction materials in power plants change as a result of exposure to aqueous environments. The susceptibility of the materials to different forms of corrosion is influenced by the properties of these oxide films. The structure and electrochemical properties of the oxide films are in turn dependent on the applied water chemistry. Therefore, water chemistry control has been used in minimising the impact of different corrosion phenomena in operating power plants. Since there is not only one ideal operational specification for all light water reactors, individually designed water chemistry programs are needed to take into account plant-specific design features and particular problem areas. The applicability of alternative water chemistry practices require fast and reliable in-line electrochemical techniques to monitor possible changes in the oxidation behaviour of nuclear power plant materials. This thesis summarises the work done at the Technical Research Centre of Finland over the past 10 years to increase the knowledge of factors affecting the oxidation behaviour of construction materials in aqueous coolants at high temperatures. The work started with the development of electrodes for measurement of high temperature water chemistry parameters such as pH and the corrosion potential of construction materials. After laboratory testing these electrodes were used both in test reactors and in operating nuclear power plants. These measurements showed that high temperature water chemistry monitoring may be more accurate than corresponding room temperature measurements, particularly during transient situations. However, it was also found that understanding the processes taking place within and on oxide films requires a combination of electrochemical techniques enabling characterisation of the electronic properties of these films. This conclusion resulted in development of a controlled

  9. A study on the development and application of expert system for nuclear power plant

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  10. A study on the development and application of expert system for nuclear power plant

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  11. Advanced stellarator power plants

    Miller, R.L.

    1994-01-01

    The stellarator is a class of helical/toroidal magnetic fusion devices. Recent international progress in stellarator power plant conceptual design is reviewed and comparisons in the areas of physics, engineering, and economics are made with recent tokamak design studies

  12. A study on expert system applications for nuclear power plant

    Huh, Young Hwan; Kim, Kil Yoo; Kang, Soon Ju; Park, Nam Seok; Ryu, Chan Ho; Choi, In Seon; Chung, Young Moo; Chung, Tae Eon; Yim, Chang Jae; Lee, Yoon Sang.

    1990-01-01

    The objectives of this research are 1) to develop an expert system which can automatically evaluate eddy current (EC) signal during an eddy current test (ECT) of SG U tube inspection, 2) to build an effective data base management system for ECT data. By this expert system the reliability in EC signal evaluation can be improved, and the required man-power can be reduced. And this expert system can supply a stable ECT and contribute to a safe operation of the nuclear power plant. (author)

  13. A study on safety climate at nuclear power plants

    Fukui, Hirokazu; Yoshida, Michio; Yoshiyama, Naohiro

    2001-01-01

    factors as the rating scales of the safety climate. In order to study the characteristics of the safety climate at nuclear power plants, we used a causal model with safety confirmation/report' as the result and other factors as forecasting factors. As a result of the covariance structure analysis using the causal model, it was found that 'safety confirmation/report' is an action based on confidence in knowledge and skill', and is supported by 'attitude of supervisors' and 'clarity of tasks.' The analytical results also indicate that 'safety education in workplace' plays an important role in promoting the sharing of information as a medium factor. As described, 'attitude of supervisors,' 'clarity of tasks' and 'safety education in workplace,' all of which are organizational environment factors, are important forecasting factors that influence individuals' safety actions and hence considered as constituents of the safety climate. (author)

  14. Study on reactor power change and ambiguous control of third Qinshan Nuclear Power Plant

    Wang Gongzhan

    2006-01-01

    The phenomenon of the average power reduction during long term full power operating in Third Qinshan nuclear power plant is analyzed . According to the basic conclusions of reactor power fluctuating derived by probability statistic and calculation the corresponding ambiguous control project is proposed. The operating performance could be achieved by the present controlling project is predicted additionally. (authors)

  15. Probabilistic seismic safety study of an existing nuclear power plant

    Kennedy, R.P.; Cornell, C.A.; Kaplan, S.; Perla, H.F.

    1980-01-01

    This study was conducted as part of an overall safety study of the Oyster Creek nuclear power plant. The earthquake hazard was considered as an initiating event that could result in radioactive release from the site as a result of core melt. The probability of earthquake initiated releases were compared with the probability of releases due to other initiating events. Three steps are necessary to evaluate the probability of earthquake initiated core melt. (1) estimate the ground motion (peak ground acceleration) and uncertainty in this estimate as functions of annual probability of occurrence; (2) estimate the conditional probability of failure and its uncertainty for structures, equipment, piping, controls, etc., as functions of ground acceleration; and (3) combine these estimates to obtain probabilities of earthquake induced failure and uncertainties in such estimates to be used in event trees, system models, and fault trees for evaluating the probability of earthquake induced core melt. This paper concentrates on the first two steps with emphasis on step 2. The major difference between the work presented and previous papers is the development and use of uncertainty estimates for both the ground motion probability estimates and the conditional probability of failure estimates. (orig.)

  16. Study on the radiological Impact of Coal Fired Power Plants

    Cancio, D.; Robles, B.; Mora, J. C.; Baeza, A.; Corbacho, J. A.; Vasco, J.; Guillen, J.

    2008-01-01

    The study is part of the goal set forth in Title VII of the European Basic Safety Standards and the Spanish regulations on radiation protection related to work activities that may involve a significant increase in exposure of workers and the public to natural radiation. Coal contains small quantities of radionuclides in the series of uranium, thorium and potassium which in the industrial process can lead to radiological exposure. This work presents the measurements and evaluations conducted in one of the power plants object of study: The Unidad Termica de Produccion de Litoral in the Almeria Province. The maximum dose assessed for workers are in the order of 0.14 mSv per year and in the order of 0.05 mSv per year for the public in the realistic scenarios considered. These values are well below the 1mSv per year reference levels, recommended in Europe to have some interest from the radiation protection point of view. (Author) 52 refs

  17. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2000-01-01

    Fundamentals on the plan, the national policy, the safety securities for the life extension of the nuclear power plant was established from the domestic/abroad documents and case studies in relation with the life extension and decommissioning of the nuclear power plant. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the domestic/abroad standard of the decommissioning (decontamination. dismantling) technology and regulation. Moreover, the study on the cost estimation method has been carried out for the decommissioning of the nuclear power plant. (author)

  18. A fundamental study on nuclear power plant diagnosis system

    Yoshimura, Sei-ichi; Fujimoto, Junzo

    1987-01-01

    Diagnosis of nuclear power plant is a large application field of knowledge engineering. But, the study examples are few and the diagnosis method is not established yet. This report describes the diagnosis method using cross correlation coefficients and describes the knowledge acquisition method of undefined transients in order to enhance the system performance. The usefulness of the system was verified by putting some data into the system. Main results are as follows. (1) Diagnosis method. Some transients are selected by the first judgement and one of them is identified by the second judgement using the cross correlation. (2) Knowledge aquisition method. When putting new data into the knowledge-base, the system indicates the inconsistency by arranging the aquired data, and the operators input new transient names and corresponding manipulation methods after analyzing the indicated results. (3) Usefulness of the system. Freedwater controller failures(2 transients), 2 recirculation pumps trip and a dummy datum combined 2 transients(one is feedwater controller failure and one is 2 recirculation pumps trip) were put into the system. It was proved that the system identified the transients correctly and it indicated the first hit and the inconsisency of the transients in the course of knowledge acquisition. (author)

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

    Danzmann, H.J.

    1981-01-01

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

  20. Nuclear power plant diagnostics study at the Midland Training Simulator

    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

  1. Capital cost: pressurized water reactor plant. Commerical electric power cost studies

    1977-06-01

    The investment cost study for the 1139-MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume includes in addition to the foreword and summary, the plant description and the detailed cost estimate

  2. Fatigue damage in nuclear power plants: cases study

    Goltrant, O.; Thebault, Y.

    2001-01-01

    Some fatigue cracks have been detected on nuclear power plants components. Generally they appears under local solicitations not correctly predicted. Two cases are presented in this paper to illustrate the problem: the pitting during mechanical fatigue where the stresses are induced by the pumps vibrations or by fluid flow; the mixing zones of RRA circuit (N4 bearing) where the stresses are induced by the flow of different temperature fluids. The examination allowed the identification of the cracking origin and the development of corrective solutions. (A.L.B.)

  3. A study on safety climate at nuclear power plants

    Fukui, Hirokazu [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Yoshida, Michio; Yoshiyama, Naohiro [Japan Institute for Group Dynamics, Fukuoka (Japan)

    2001-09-01

    ;safety education in workplace' and 'clarity of tasks.' Hence, we have decided to use these three organizational environment factors as the rating scales of the safety climate. In order to study the characteristics of the safety climate at nuclear power plants, we used a causal model with safety confirmation/report' as the result and other factors as forecasting factors. As a result of the covariance structure analysis using the causal model, it was found that 'safety confirmation/report' is an action based on confidence in knowledge and skill', and is supported by 'attitude of supervisors' and 'clarity of tasks.' The analytical results also indicate that 'safety education in workplace' plays an important role in promoting the sharing of information as a medium factor. As described, 'attitude of supervisors,' 'clarity of tasks' and 'safety education in workplace,' all of which are organizational environment factors, are important forecasting factors that influence individuals' safety actions and hence considered as constituents of the safety climate. (author)

  4. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young

    2016-01-01

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety

  5. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young [KHNP, Daejeon (Korea, Republic of)

    2016-10-15

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety.

  6. Results from study of potential early commercial MHD power plants and from recent ETF design work

    Hals, F.; Kessler, R.; Swallom, D.; Westra, L.; Zar, J.; Morgan, W.; Bozzuto, C.

    1980-06-01

    The study deals with different 'moderate technology' entry-level commercial MHD power plants. Two of the reference plants are based on combustion of coal with air preheated in a high-temperature regenerative air heater separately fired with a low-BTU gas produced in a gasifier integrated with the power plant. The third reference plant design is based on the use of oxygen enriched combustion air. Performance calculations show that an overall power plant efficiency of the order of 44% can be reached with the use of oxygen enrichment.

  7. On nuclear power plant uprating

    Ho, S. Allen; Bailey, James V.; Maginnis, Stephen T.

    2004-01-01

    Power uprating for commercial nuclear power plants has become increasingly attractive because of pragmatic reasons. It provides quick return on investment and competitive financial benefits, while involving low risks regarding plant safety and public objection. This paper briefly discussed nuclear plant uprating guidelines, scope for design basis analysis and engineering evaluation, and presented the Salem nuclear power plant uprating study for illustration purposes. A cost and benefit evaluation of the Salem power uprating was also included. (author)

  8. Study on laser beam welding technology for nuclear power plants

    Chida, Itaru; Shiihara, Katsunori; Fukuda, Takeshi; Kono, Wataru; Obata, Minoru; Morishima, Yasuo

    2012-01-01

    Laser beam welding is one of the jointing processes by irradiating laser beam on the material surface locally and widely used at various industrial fields. Toshiba has developed various laser-based maintenance and repair technologies and already applied them to several existing nuclear power plants. Laser cladding is a technique to weld the corrosion resistant metal onto a substrate surface by feeding filler wire to improve the corrosion resistance. Temper-bead welding is the heat input process to provide the desired microstructure properties of welded low alloy steels without post weld heat treatment, by inducing proper heat cycle during laser welding. Both laser welding technologies would be performed underwater by blowing the shielding gas for creating the local dry area. In this report, some evaluation results of material characteristics by temper-bead welding to target at Reactor Coolant System nozzle of PWR are presented. (author)

  9. Micrometeorological study of the Atucha Nuclear Power Plant site

    Berri, G.J.; Robbio, C.A.

    1986-01-01

    The evaluation of time meteorological data obtained at the micrometeorological station of the Atucha Power Plant during 1979, is presented. Special attention is given to the transport and atmospheric dispersion characteristics through the evaluation of the mean and hourly wind behaviour and the stability classes. Furthermore, it is obtained an estimation of the dispersion factors both for short-term and long-term releases using Gaussians models. As these factors are representative of mean conditions, they should not be applied to the analysis of isolated situations. Finally it is emphasized that, although the results were obtained by means of 1979 data, significative differences are not expected for other years. (M.E.L.) [es

  10. Study on Quaternary ground siting of nuclear power plant, (1)

    Kokusho, Takaji; Nishi, Koichi; Honsho, Shizumitsu

    1991-01-01

    A seismic stability evaluation method for a nuclear power plant to be located on a Quaternary sandy/gravelly ground is discussed herein in terms of the geological and geotechnical survey, design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock-foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil samplings will play a major role in this case. The design earthquake input spectrum for this siting is proposed so as to take account the significant effect of longer period motion on the ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

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

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

    2011-01-01

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

  12. Human performance and reliability studies on nuclear power plant

    Miyaoka, S.

    1988-01-01

    The TMI accident in USA, the Chernobyl accident in USSR and other major accidents overseas have shown that it is necessary to investigate and research human factor problems related to operation, maintenance and others in order to increase the safety and reliability of nuclear power plants. Although a variety of countermeasures have been devised, the accidents and failures due to human factors still occur. So far, the problems related to human factors have not been fundamantally and systematically investigated. Also the data base related to this problem has not been developed. Therefore, the government and electric utility industry began the research on the prevention of the accidents caused by human errors. The basic research is carried out by the government, and the applied research is done by electric utility industry. The Central Research Institute of Electric Power Industry established the Human Factors Research Center on July 1, 1987. The research program in the Human Factors Research Center is divided into the basic research to clarity fundamental human characteristics, the systematic research to apply this information and the analytical research on human error experience. These research activities are reported. (Kako, I.)

  13. Engineering management at feasibility study stage of nuclear power plant under EPC mode

    Wang Zhiqiang

    2015-01-01

    After the investment reform by the State Council in 2004, NDRC carries out approval system for enterprises to invest in nuclear power plants. Feasibility study stage is a critical stage on the mainline of nuclear power project approval, which intersects with the license application, and engineering design. The owners of nuclear power plants are required stringently in engineering management. From the owners' management point of view under EPC mode, this paper sorts the preliminary project process for nuclear power plants, focusing on the management in the feasibility study stage. License application and engineering design management in the feasibility study stage are also discussed. (author)

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

    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)

  15. German study on the risks of nuclear power plants

    Wollny, V.

    1987-01-01

    The 'Deutsche Risikostudie Kernkraftwerke', DRS, (German study on the risks of nuclear plants) calculates a frequency of 1/10000 years (i.e. once in 10000 years of reactor operation) for the event of insufficient cooling of the reactor core occurring. The resulting collective risk is put at approximately 10 deaths per year for 25 plants. As the explanations show, the error margin of such a risk statement is enormous. Moreover, much seems to indicate that the risk was underrated. Apart from this, risk analyses are of doubtful value in the decision process for or against the introduction of large-scale technologies. They cannot replace the individual decision of all concerned. (orig./HSCH) [de

  16. Technical Feasibility Study of Thermal Energy Storage Integration into the Conventional Power Plant Cycle

    Jacek D. Wojcik

    2017-02-01

    Full Text Available The current load balance in the grid is managed mainly through peaking fossil-fuelled power plants that respond passively to the load changes. Intermittency, which comes from renewable energy sources, imposes additional requirements for even more flexible and faster responses from conventional power plants. A major challenge is to keep conventional generation running closest to the design condition with higher load factors and to avoid switching off periods if possible. Thermal energy storage (TES integration into the power plant process cycle is considered as a possible solution for this issue. In this article, a technical feasibility study of TES integration into a 375-MW subcritical oil-fired conventional power plant is presented. Retrofitting is considered in order to avoid major changes in the power plant process cycle. The concept is tested based on the complete power plant model implemented in the ProTRAX software environment. Steam and water parameters are assessed for different TES integration scenarios as a function of the plant load level. The best candidate points for heat extraction in the TES charging and discharging processes are evaluated. The results demonstrate that the integration of TES with power plant cycle is feasible and provide a provisional guidance for the design of the TES system that will result in the minimal influence on the power plant cycle.

  17. Improving human reliability through better nuclear power plant system design: Program for advanced nuclear power studies

    Golay, M.W.

    1993-01-01

    The project on ''Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performance'' was been undertaken in order to address the problem of human error in advanced nuclear power plant designs. Lack of a mature theory has retarded progress in reducing likely frequencies of human errors. Work being pursued in this project is to perform a set of experiments involving human subjects who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants, which are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds

  18. Study of aging effects in PWR power plants components - 15043

    Silva Borges, D. da; Lava, D.D.; Guimaraes, A.C.F.; Moreira, M. de L.

    2015-01-01

    In this paper we present a simulation about the aging process of the containment spray injection system (CSIS) of a pressurized water reactor (PWR) using the fault tree method (FT). The FT has the capacity to present the logic of events that leads to system unavailability, to capture frequency estimation of events, to model and calculate hazardous events frequency (before they happen) and help developing protective layers. The Monte Carlo method and Fussell-Vesely importance measure are used in this paper to determine the system unavailability probability and the most sensitive events to the aging process. The injection system fault tree consists of a main tree and 10 sub-trees. The main tree is composed of 35 basic events, 5 gates and 1 top event. The paper details the methodology. It can be seen that the increase of the failure rate of components due to the aging process, generates the increase in the general unavailability of the system that contains these components. The extension of the operating life of nuclear power plant must be accompanied by a special attention to the aging process of its components

  19. Purchasing and supply quality management in a power plant : a case study

    2012-01-01

    M. Ing. This research study aims at presenting the management of quality problem issues that often result from procured items in a power plant. The motivation for carrying out this research was an unacceptable risk of undesirable impact on plant availability, or operating costs that arises from quality problem issues of procured items in a particular power plant. In this dissertation, the author aims to provide an overview of quality management and procurement management, by focusing on ho...

  20. Numerical study of evaporators in power plants for improved dynamic fl exibility

    Johansen, Axel Vodder Ohrt

    The main objective of this Ph.D. thesis is to describe and analyse the most recent knowledge about operational flexibility in steam power plant evaporators, based on mathematical / numerical methods. The thesis addresses a mathematical study of steam power plant evaporators and involves the reader...... will be introduced to basic concepts in the power sector, including lifetime terms, such as corrosion, creep and fatigue, related to the evaporator tubes, which are responsible for the transfer of energy from the boiler to the water / steam circuit of a power plant. New evaporator technologies are briefly described......, followed by a simulation of a steam power plant evaporator of Skærbækværket (SKV3), which is one of DONG Energy’s ten central CHP plants, built in 1998 and located in Skærbæk at the mouth of Kolding Fjord in Denmark. Here different heating profiles of the evaporator are investigated, as well...

  1. Hydroelectric Power Plants Dobsina

    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

  2. Feasibility study on floating nuclear power plant (1). Conceptual design study of FNPP. Contract research

    Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki; Takahashi, Masao; Nakazawa, Toshio

    2001-02-01

    Offshore siting methods for a nuclear power plant are classified into three types as a floating type, a settled type and a land reclamation type. The floating nuclear power plant (FNPP) has a number of advantages, such as seismic isolation, standardization of design and manufacturing, and reduction of construction period. It is, however, required for FNPP to establish the safety standards, which are different from ones for land based nuclear power plant. Investigations for this subject have not been conducted sufficiently. In this report, design study on a concept for FNPP and a review on stability evaluation for the floating platform, which were performed in order to study the safety concept of the FNPP are described. The basic concept of the FNPP are described. The basic concept for FNPP is as follows: The FNPP is sited approximately 1 - 2km off the sea coast on the open sea with water depth of about 20m and it is moored of protected sea by the breakwater, it provide a floating platform for a 1,100MWe class PWR plant. The results of design study show that the floating platform for 1,100MWe class PWR plant of 300m (L) x 80m (W) x 35m (H), and displacement of approximately 300,000 ton can be constructed in a dockyard. This floating platform guarded by the breakwater is found to be stable enough to install the nuclear power plant from the analysis simulating the movement of the platform due to sea wave or wind. (author)

  3. Feasibility study on floating nuclear power plant (1). Conceptual design study of FNPP. Construct research

    Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki [Department of Nuclear Energy System, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Takahashi, Masao [Niigata Engineering Co. Ltd., Tokyo (Japan); Nakazawa, Toshio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Sato, Kazuo [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

    2001-02-01

    Offshore siting methods for a nuclear power plant are classified into three types as a floating type, a settled type and a land reclamation type. The floating nuclear power plant (FNPP) has a number of advantages, such as seismic isolation, standardization of design and manufacturing, and reduction of construction period. It is, however, required for FNPP to establish the safety standards, which are different from ones for land based nuclear power plant. Investigations for this subject have not been conducted sufficiently. In this report, design study on a concept for FNPP and a review on stability evaluation for the floating platform, which were performed in order to study the safety concept of the FNPP are described. The basic concept of the FNPP are described. The basic concept for FNPP is as follows: The FNPP is sited approximately 1 - 2km off the sea coast on the open sea with water depth of about 20m and it is moored of protected sea by the breakwater, it provide a floating platform for a 1,100MWe class PWR plant. The results of design study show that the floating platform for 1,100MWe class PWR plant of 300m (L) x 80m (W) x 35m (H), and displacement of approximately 300,000 ton can be constructed in a dockyard. This floating platform guarded by the breakwater is found to be stable enough to install the nuclear power plant from the analysis simulating the movement of the platform due to sea wave or wind. (author)

  4. STUDY OF PLANT-WIDE CONTROL IMPLEMENTATION IN PRODUCTION PROCESS OF GEOTHERMAL POWER PLANT

    KATHERIN INDRIAWATI

    2017-02-01

    Full Text Available The design of plant-wide control system to optimize electricity production in geothermal power plant is proposed in this research. The objective is to overcome the deficiency due to changes in the characteristics of production well and fluctuation in electricity demand load. The proposed plant-wide control system has two main tasks; to maintain production process at optimum value and to increase efficiency. The pressure in separator and condenser is maintained at the respective set points under electrical load fluctuations in order to ensure optimum efficiency. The control system also reduce the usage of auxialiary electrical power and increase efficiency. The task was performed by controlling inlet cooling water temperatures to the condenser. It was concluded that the proposed control structure was able to increase efficiency and maintain production.

  5. Virtual power plant feasibility study and funding proposal / the virtual power plant objectives, concept, components, context, business plan / objectives, activities and timelines for the VPP feasibility study

    MacDonald, A.

    2004-01-01

    This paper presents a proposal for funding a virtual power plant feasibility study. The goals of the virtual power plant are to increase the efficiency of electricity use by creating a market-driven, subsidy-free, financially sustainable mechanism to finance economic Demand Side Management (DSM) by providing a fully liquid market for saved electricity, provide a new revenue opportunity for the Local Distributing Company (LDC) and increase the use of renewable and low environmental impact, high efficiency technologies within the service area

  6. Marginal costs of water savings from cooling system retrofits: a case study for Texas power plants

    Loew, Aviva; Jaramillo, Paulina; Zhai, Haibo

    2016-10-01

    The water demands of power plant cooling systems may strain water supply and make power generation vulnerable to water scarcity. Cooling systems range in their rates of water use, capital investment, and annual costs. Using Texas as a case study, we examined the cost of retrofitting existing coal and natural gas combined-cycle (NGCC) power plants with alternative cooling systems, either wet recirculating towers or air-cooled condensers for dry cooling. We applied a power plant assessment tool to model existing power plants in terms of their key plant attributes and site-specific meteorological conditions and then estimated operation characteristics of retrofitted plants and retrofit costs. We determined the anticipated annual reductions in water withdrawals and the cost-per-gallon of water saved by retrofits in both deterministic and probabilistic forms. The results demonstrate that replacing once-through cooling at coal-fired power plants with wet recirculating towers has the lowest cost per reduced water withdrawals, on average. The average marginal cost of water withdrawal savings for dry-cooling retrofits at coal-fired plants is approximately 0.68 cents per gallon, while the marginal recirculating retrofit cost is 0.008 cents per gallon. For NGCC plants, the average marginal costs of water withdrawal savings for dry-cooling and recirculating towers are 1.78 and 0.037 cents per gallon, respectively.

  7. CNE (Embalse nuclear power plant): probabilistic safety study. Electric power supply. Events sequence

    Figueroa, N.

    1987-01-01

    The plant response to the occurrence of the starting event 'total loss of electric power supply to class IV and class III' is analyzed. This involves the study of automatical actions of safety and process systems as well as the operator actions. The probabilistic evaluation of starting event frequency is performed through fault-tree techniques. The frequency of occurrence 'loss of electric power supply to class IV (λIV = 0.56/year) and the probability of failure to demand of 'reserve' generating groups (Pd III 6.79 x 10 -3 ) contribute to the mentioned frequency. As soon as the starting event occurs, the reactor power must be reduced to 0%, the fuel must be cooled through the thermo siphon and decay heat has to be removed. The events sequence analysis leads to the conclusion that the non shutting down of the reactor with any of the shutdown systems is 'incredible' (10 -6 /year). In all cases the fuel is cooled by building the thermo siphon except when a substantial inventory loss exist due to a closure failure of some valve of pressure and inventory control system. The order of magnitude of the failure of decay heat removal through the steam generators is 4 x 10 -4 . This removal would be assured by the emergency water system. Therefore, the frequency of the sequence of possible core meltdown, when the reactor does not shut down is: λ = 5 x 10 -9 /year and for the failure of heat removal: λ = 2 x 10 -6 /year. (Author)

  8. Nuclear plant power up-rate study: feedwater heater evaluations

    Svensson, Eric; Catapano, Michael; Coakley, Michael; Thomas, Dan

    2014-01-01

    Given today's nuclear industry business climate, it has become common for Utility companies to consider increasing unit capacities through turbine replacement and power up-rates. An integral part of the studies conducted by many towards this end, involve the generation of a set of turbine cycle heat balances with predicted performance parameters for the up-rated condition. Once these tentative operating values are established, it becomes necessary to evaluate the suitability of the existing components within each system to ensure they are capable of continued safe and reliable operation. The ultimate cost for the up-rate, including the cost for any major required modifications or significant replacements is weighed against increased revenue generated from the up-rate over time. Exelon's Peach Bottom Atomic Power Station (PBAPS) is currently planning for an Extended Power up-rate (EPU) for both units. To ensure the existing Feedwater Heaters (FWH) could maintain the operating and transient response margins at the EPU condition, an engineering study was conducted. Powerfect Inc. in conjunction with SPX Heat Transfer LLC were contracted to provide engineering services to analyze the design, thermal performance, reliability and operating conditions at projected EPU conditions. Specifically, to address the following with regard to the station's Feedwater Heaters (FWHs): 1. Evaluate Drain Cooler (DC) Velocities - including zone inlet velocity, cross and window velocities and outlet velocities. 2. Evaluate Drain Cooler Zone Pressure Drop for effect on drain cooler margins to flashing. 3. Evaluate differential pressure allowable across the pass partition plate. 4. Evaluate Drain Cooler Tube Vibration Potential. 5. Perform detailed steam dome velocity calculations. The goal of the study was to identify the most susceptible areas within the heaters for problems and potential failures when operating at the higher duty of the EPU condition for the remaining life

  9. Small hydroelectric power plants

    Helgesen, Boerre

    2002-01-01

    Small hydroelectric power plants are power plants of 1 - 10 MW. For a supplier, this is an unnatural limit. A more natural limit involves compact engine design and simplified control system. The article discusses most of the engine and electrotechnical aspects in the development, construction and operation of such a plant

  10. A study on the water chemistry in nuclear power plants

    Chae, Sung Ki; Yang, Kyung Rin; Koo Je Hyoo; Lee, Eun Hee; Kim, Joung Soo; Jang, Soon Shik; Park, Su Hoon; Song, Myung Ho; Jeon, Kyung Soo

    1987-12-01

    Significant corrosion-failures occurring in the important components or facilities in the secondary-side system cause various problems in safety due to the leakage of radioactive substances and consequently induce the reduction of the operational efficiency of the plants. In addition, the replacement of the failed components or facilities results in the tremendous expenses and a long term shutdown. The objective of the research was to ensure the safety and integrity of the plants, to improve the efficiency of the plant operation, and to prevent the shortening of plant life by improving the controlling technique of the water chemistry and minimizing the corrosion-failures in the important components and/or facilities of the plants

  11. Regional geology, tectonic, geomorphology and seismology studies to interest to nuclear power plants at Itaorna beach

    Hasui, Y.; Almeida, F.F.M. de; Mioto, J.A.; Melo, M.S. de.

    1982-01-01

    The study prepared for the nuclear power plants to be located at Itaorna comprised, the analysis and integration of Geologic, tectonic, geomorphologic and seismologic information and satisfactory results of regional stability were obtained. (L.H.L.L.) [pt

  12. Capital cost: pressurized water reactor plant. Commercial electric power cost studies

    1977-06-01

    The investment cost study for the 1139 MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume contains the drawings, equipment list and site description.

  13. Capital cost: pressurized water reactor plant. Commercial electric power cost studies

    1977-06-01

    The investment cost study for the 1139 MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume contains the drawings, equipment list and site description

  14. Critical channel power calculation for nominal operation in the CNE (Embalse nuclear power plant): sensitivity study

    Garcia, A.E.; Parkansky, D.G.

    1993-01-01

    In the Embalse nuclear power plant (CNE), the Regional Overpower Protection System acting on the Shutdown Systems number 1 and number 2 protects the reactor against overpowers in the reactor field for a localized peaking or a power increase in the reactor as a whole. This report summarizes the results of the critical channel power calculation for the time average powers configuration for the 380 reactor field channels. The final purpose of this work is to analyze and eventually modify the detector set points. Other reactor configurations are being analyzed. The report also presents a sensitivity analysis in order to evaluate potential sources of error and uncertainties which could affect the ROP performance. (author)

  15. Numerical Boron mixing studies for Loviisa Nuclear Power Plant

    Gango, P. [IVO International Ltd. (Finland)

    1995-09-01

    A program has been started for studying numerically boron mixing in the downcomer of Loviisa NPP (VVER-440). Mixing during the transport of a diluted slug from the loop to the core might serve as an inherent protection mechanism against severe reactivity accidents in inhomogenous boron dilution scenarios for PWRs. The commercial general purpose Computational Fluid Dynamics (CFD) core PHOENICS is used for solving the governing fluid flow equations in the downcomer geometry of VVER-440. So far numerical analyses have been performed for steady state operation conditions and two different pump driven transients. The steady state analyses focused on model development and validation against existing experimental data. The two pump driven transient scenarios reported are based on slug transport during the start of the sixth and first loop respectively. The results from the two transients show that mixing is case and plant specific; the high and open downcomer geometry of VVER-440 seems to be advantageous from mixing point of view. In addition the analyzing work for the {open_quotes}first pump start{close_quotes} scenario brought up some considerations about flow distribution in the existing experimental facilities.

  16. Less power plants

    TASR

    2003-01-01

    In the Slovak Republic the number of company power plants decreased as against 2001 by two sources. In present time only 35 companies have their own power plants. The companies Slovnaft, Kappa Sturovo, Slovensky hodvab Senica, Matador Puchov, Maytex Liptovsky MikuIas, Kovohuty Krompachy, Chemko Strazske and some Slovak sugar factories belong to the largest company power plants in force of distributing companies. Installed output of present 35 company sources is 531 MW. The largest of separate power plants as Paroplynovy cyklus Bratislava (218 MW) and VD Zilina (72 MW) belong to independent sources. Total installed output of Slovak sources was 8306 MW in the end of last year

  17. Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde

    Tijerina S, F.; Cruz G, M.; Amador C, C.

    2013-10-01

    In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

  18. German risk study nuclear power plants, phase B

    1990-01-01

    The book documents the results of the probabilistic safety analysis performed at the Biblis-B reference plant. It covers 1) result course analyses and reliability analyses of loss of coolant accidents and transients without and with regard to on-site emergency measures; 2) event tree analyses of on-site and off-site events; 3) analyses of the function of the safety tank in the case of core meltdown accidents, and of the release of fission products into the environment in such case. The probability of a core meltdown is about 3-4 to 100,000 per year and plant. (HP) [de

  19. Final report for the field-reversed configuration power plant critical-issue scoping study

    Santarius, John F.; Mogahed, Elsayed A.; Emmert, Gilbert A.; Khater, Hesham Y.; Nguyen, Canh N.; Ryzhkov, Sergei V.; Stubna, Michael D.; Steinhauer, Loren C.; Miley, George H.

    2001-03-01

    This report describes research in which a team from the Universities of Wisconsin, Washington, and Illinois performed a scoping study of critical issues for field-reversed configuration (FRC) power plants. The key tasks for this research were (1) systems analysis of deuterium-tritium (D-T) FRC fusion power plants, and (2) conceptual design of the blanket and shield module for an FRC fusion core.

  20. Solar thermal power plants

    Schnatbaum, L.

    2009-01-01

    The solar thermal power plant technology, the opportunities it presents and the developments in the market are outlined. The focus is on the technology of parabolic trough power plants, a proven technology for solar power generation on a large scale. In a parabolic trough power plant, trough-shaped mirrors concentrate the solar irradiation onto a pipe in the focal line of the collector. The thermal energy thus generated is used for electricity generation in a steam turbine. Parabolic trough plants can be combined with thermal storage and fossil or biomass fired heat exchangers to generate electricity even when the sun is not shining. Solar Millennium AG in Erlangen has developed the first power plant of this kind in Europe. After two years of construction the plant started operation in Southern Spain in 2008. This one and its sister projects are important steps leading the way for the whole market. The paper also covers the technological challenges, the key components used and the research and development activities concerning this technology. Solar thermal power plants are ideal for covering peak and medium loads in power grids. In hybrid operation they can also cover base-load. The Solar Chimney power plant, another striking technology for the conversion of solar into electric energy, is described briefly. The paper concludes with a look at the future - the import of solar energy from the deserts of North Africa to central Europe. (author)

  1. Power plant chemical technology

    NONE

    1996-12-01

    17 contributions covering topies of fossil fuel combustion, flue gas cleaning, power plant materials, corrosion, water/steam cycle chemistry, monitoring and control were presented at the annual meeting devoted to Power Plant Chemical Technology 1996 at Kolding (Denmark) 4-6 September 1996. (EG)

  2. Nuclear Power Plants. Revised.

    Lyerly, Ray L.; Mitchell, Walter, III

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

  3. NUCLEAR POWER PLANT

    Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

    1963-05-14

    A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

  4. The Kuroshio power plant

    Chen, Falin

    2013-01-01

    By outlining a new design or the Kuroshio power plant, new approaches to turbine design, anchorage system planning, deep sea marine engineering and power plant operations and maintenance are explored and suggested. The impact on the local environment, particularly in the face of natural disasters, is also considered to provide a well rounded introduction to plan and build a 30MW pilot power plant. Following a literature review, the six chapters of this book propose a conceptual design by focusing on the plant's core technologies and establish the separate analysis logics for turbine design and

  5. Nuclear power plants

    Margulova, T.Ch.

    1976-01-01

    The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

  6. A study of public acceptance of construction of atomic power plant

    Harada, Kazunori; Matsuhashi, Ryuji; Yoshida, Yoshikuni

    2011-01-01

    In June 2010, Basic Energy Plan was approved in a Cabinet meeting. It says that Japan aims to construct more than 14 atomic power plants by 2030. Today, there are 12 plans of construction of atomic power plant, but it is hard to say that their plans easily come off. That's because public acceptance of atomic power plant is low in Japan, for example local residents wage opposition campaigns. This study conducts a survey in the form of a questionnaire and analyzes it by Analytical Hierarchical Process (AHP). Analytic Hierarchy Process is a structured technique for dealing with complex decisions. A questionnaire using AHP is very easy to answer and analyze. This survey was conducted in 2 areas. First area is Hohoku-cho, Yamaguchi Pref. that had a plan of construction of atomic power plant and the plan was demolished by opposition campaigns. Second area is Kaminoseki-cho, Yamaguchi Pref. that has a plan of construction of atomic power plant now and the plan is working order. Public acceptance can be calculated from survey data of 2 areas, and it helps to understand why first area disapproved a plan of atomic power plant and second area approves it. We consider a model to analyze public acceptance. (author)

  7. Shamir secret sharing scheme with dynamic access structure (SSSDAS). Case study on nuclear power plant

    Thiyagarajan, P.; Thandra, Prasanth Kumar; Rajan, J.; Satyamurthy, S.A.V. [Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India). Computer Div.; Aghila, G. [National Institute of Technology, Karaikal (India). Dept. of Computer Science and Engineering

    2015-05-15

    In recent years, due to the sophistication offered by the Internet, strategic organizations like nuclear power plants are linked to the outside world communication through the Internet. The entry of outside world communication into strategic organization (nuclear power plant) increases the hacker's attempts to crack its security and to trace any information which is being sent among the top level officials. Information security system in nuclear power plant is very crucial as even small loophole in the security system will lead to a major disaster. Recent cyber attacks in nuclear power plant provoked information security professionals to look deeply into the information security aspects of strategic organizations (nuclear power plant). In these lines, Shamir secret sharing scheme with dynamic access structure (SSSDAS) is proposed in the paper which provides enhanced security by providing dynamic access structure for each node in different hierarchies. The SSSDAS algorithm can be applied to any strategic organizations with hierarchical structures. In this paper the possible scenarios where SSSDAS algorithm can be applied to nuclear power plant is explained as a case study. The proposed SSSDAS scheme identifies the wrong shares, if any, used for reconstruction of the secret. The SSSDAS scheme also address the three major security parameters namely confidentiality, authentication and integrity.

  8. Shamir secret sharing scheme with dynamic access structure (SSSDAS). Case study on nuclear power plant

    Thiyagarajan, P.; Thandra, Prasanth Kumar; Rajan, J.; Satyamurthy, S.A.V.; Aghila, G.

    2015-01-01

    In recent years, due to the sophistication offered by the Internet, strategic organizations like nuclear power plants are linked to the outside world communication through the Internet. The entry of outside world communication into strategic organization (nuclear power plant) increases the hacker's attempts to crack its security and to trace any information which is being sent among the top level officials. Information security system in nuclear power plant is very crucial as even small loophole in the security system will lead to a major disaster. Recent cyber attacks in nuclear power plant provoked information security professionals to look deeply into the information security aspects of strategic organizations (nuclear power plant). In these lines, Shamir secret sharing scheme with dynamic access structure (SSSDAS) is proposed in the paper which provides enhanced security by providing dynamic access structure for each node in different hierarchies. The SSSDAS algorithm can be applied to any strategic organizations with hierarchical structures. In this paper the possible scenarios where SSSDAS algorithm can be applied to nuclear power plant is explained as a case study. The proposed SSSDAS scheme identifies the wrong shares, if any, used for reconstruction of the secret. The SSSDAS scheme also address the three major security parameters namely confidentiality, authentication and integrity.

  9. Human Reliability analysis for digitized nuclear power plants: Case study on the LingAo II nuclear power plant

    Zou, Yan Hua; Zhang, Li [Institute of Human Factors Engineering AND Safety Management, Hunan Institute of Technology, Hengyang (China); Dai, Cao; Li, Peng Cheng; Qing, Tao [Human Factors Institute, University of South China, Hengyang (China)

    2017-03-15

    The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

  10. Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

    Yanhua Zou

    2017-03-01

    Full Text Available The main control room (MCR in advanced nuclear power plants (NPPs has changed from analog to digital control system (DCS. Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

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

    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)

  12. Distributed power generation: A case study of small scale PV power plant in Greece

    Bakos, G.C. [Democritus University of Thrace, Department of Electrical and Computer Engineering, Laboratory of Energy Economics, 67 100 Xanthi (Greece)

    2009-09-15

    In recent years, energy systems have been undergoing a development trend characterised by privatisation of the most important energy sectors (electricity and natural gas) that has turned former monopolies into free-market competitors. Furthermore, community awareness of environmental impact caused by large conventional power plants is growing, together with a greater interest in distributed-generation (DG) technologies based upon renewable energy sources (RES) and cogeneration. In this context, renewable energy technologies are emerging as potentially strong competitors for more widespread use. Despite the remarkable progress attained over the past decades, RES have not yet been fully integrated into the power sector. Some RES-technologies have already achieved a significant market share. The industry is now quite mature, although far from having developed its global potential. This paper deals with the current status of DG in Greece and the presentation of a 60 kWp PV power station, developed under Law 3468/06 ''Production of Electricity from Renewable Energy Sources, High Efficiency Cogeneration of Heat and Power and Other De{nu}ices''. This application is the first DG installation with fixed PV modules implemented in the country after the approval of Law 3468/06. Cash flow economic analysis of the developed DG installation is performed and the experiences related to the potential of DG in Greek electricity market is presented and discussed. (author)

  13. Distributed power generation: A case study of small scale PV power plant in Greece

    Bakos, G.C.

    2009-01-01

    In recent years, energy systems have been undergoing a development trend characterised by privatisation of the most important energy sectors (electricity and natural gas) that has turned former monopolies into free-market competitors. Furthermore, community awareness of environmental impact caused by large conventional power plants is growing, together with a greater interest in distributed-generation (DG) technologies based upon renewable energy sources (RES) and cogeneration. In this context, renewable energy technologies are emerging as potentially strong competitors for more widespread use. Despite the remarkable progress attained over the past decades, RES have not yet been fully integrated into the power sector. Some RES-technologies have already achieved a significant market share. The industry is now quite mature, although far from having developed its global potential. This paper deals with the current status of DG in Greece and the presentation of a 60 kWp PV power station, developed under Law 3468/06 ''Production of Electricity from Renewable Energy Sources, High Efficiency Cogeneration of Heat and Power and Other Deνices''. This application is the first DG installation with fixed PV modules implemented in the country after the approval of Law 3468/06. Cash flow economic analysis of the developed DG installation is performed and the experiences related to the potential of DG in Greek electricity market is presented and discussed. (author)

  14. Study on application of Doppler SODAR as meteorological observation tool at nuclear power plant

    Katayose, Naoto; Akai, Yukio.

    1993-01-01

    Among the remote sensing devices usable for meteorological observation, which became possible with the advent of modern science and technology, Doppler SODAR was selected for further study aimed at its practical application for nuclear power plants. This device was installed for testing purpose at a Japanese nuclear power and data collection (wind speed and direction) was carried out throughout one year there. The data on the selected SODAR have shown a correlation with those collected by the conventional method which is good enough to justify the SODAR's practical use at nuclear power plants. (author)

  15. The effects of power plant passage on zooplankton mortalities: Eight years of study at the Donald C. Cook Nuclear Plant

    Evans, M.S.; Warren, G.J.; Page, D.I.

    1986-01-01

    Zooplankton mortalities resulting from passage through the Donald C. Cook Nuclear Plant (southeastern Lake Michigan) were studied over an 8-year (1975-1982) period. The power plant operated at a low ΔT ( 0 C) and discharge water temperatures did not exceed 35 0 C (except September 1978). While zooplankton mortalities were significantly greater in discharge than intake waters, differences were small, averaging <3%. There was no evidence of additional delayed effects on zooplankton mortality following plant passage. There was no relationship between zooplankton mortalities and temperature (ΔT, discharge water temperature). Mechanical stresses appeared to be the major cause of zooplankton mortality. The authors hypothesize that fish predation, rather than power plant operation, probably was the major source of zooplankton mortality in inshore waters during much of the year. (author)

  16. Study on key technologies of optimization of big data for thermal power plant performance

    Mao, Mingyang; Xiao, Hong

    2018-06-01

    Thermal power generation accounts for 70% of China's power generation, the pollutants accounted for 40% of the same kind of emissions, thermal power efficiency optimization needs to monitor and understand the whole process of coal combustion and pollutant migration, power system performance data show explosive growth trend, The purpose is to study the integration of numerical simulation of big data technology, the development of thermal power plant efficiency data optimization platform and nitrogen oxide emission reduction system for the thermal power plant to improve efficiency, energy saving and emission reduction to provide reliable technical support. The method is big data technology represented by "multi-source heterogeneous data integration", "large data distributed storage" and "high-performance real-time and off-line computing", can greatly enhance the energy consumption capacity of thermal power plants and the level of intelligent decision-making, and then use the data mining algorithm to establish the boiler combustion mathematical model, mining power plant boiler efficiency data, combined with numerical simulation technology to find the boiler combustion and pollutant generation rules and combustion parameters of boiler combustion and pollutant generation Influence. The result is to optimize the boiler combustion parameters, which can achieve energy saving.

  17. Italian steam power plants

    von Rautenkranz, J

    1939-01-01

    A brief history of geothermal power production in Italy is presented. Boric acid has been produced on an industrial scale since 1818. The first electrical power was generated in 1904, and by 1939 the output of geothermal power plants had reached 500 GWh, with major expansion of facilities planned.

  18. The year 2000 power plant

    Roman, H.T.

    1989-01-01

    Every utility seeks extended service life from its existing power plants before building new ones. It is not easy to justify a new power plant. The licensing and cost of new plants have become uncertain. In response to these conditions, electric utilities are undertaking plant life-extension studies and, in some cases, reconditioning/upgrading old power plants to significantly increase useful service life. Other technologies like robotics and artificial intelligence/expert systems are also being developed to reduce operating and maintenance (O and M) expenses, to remove workers from potentially hazardous environments, and to reduce plant downtime. Together, these steps represent an interim solution, perhaps providing some relief for the next few decades. However, there are serious physical and economic limits to retrofitting new technology into existing power plants. Some old plants will simply be beyond their useful life and require retirement. In nuclear plants, for instance, retrofit may raise important and time-consuming licensing/safety issues. Based on their robotics and artificial intelligence experience, the authors of this article speculate bout the design of the year 2000 power plant - a power plant they feel will naturally incorporate liberal amounts of robotic and artificial intelligence technologies

  19. A multivariate statistical study on a diversified data gathering system for nuclear power plants

    Samanta, P.K.; Teichmann, T.; Levine, M.M.; Kato, W.Y.

    1989-02-01

    In this report, multivariate statistical methods are presented and applied to demonstrate their use in analyzing nuclear power plant operational data. For analyses of nuclear power plant events, approaches are presented for detecting malfunctions and degradations within the course of the event. At the system level, approaches are investigated as a means of diagnosis of system level performance. This involves the detection of deviations from normal performance of the system. The input data analyzed are the measurable physical parameters, such as steam generator level, pressurizer water level, auxiliary feedwater flow, etc. The study provides the methodology and illustrative examples based on data gathered from simulation of nuclear power plant transients and computer simulation of a plant system performance (due to lack of easily accessible operational data). Such an approach, once fully developed, can be used to explore statistically the detection of failure trends and patterns and prevention of conditions with serious safety implications. 33 refs., 18 figs., 9 tabs

  20. Cancer incidence in the vicinity of nuclear power plants in Taiwan: a population-based study.

    Wang, Shiow-Ing; Yaung, Chih-Liang; Lee, Long-Teng; Chiou, Shang-Jyh

    2016-01-01

    Numerous antinuclear demonstrations reveal that the public is anxious about the potential health effects caused by nuclear power plants. The purpose of this study is to address the question "Is there a higher cancer incidence rate in the vicinity of nuclear power plants in Taiwan?" The Taiwan Cancer Registry database from 1979 to 2003 was used to compare the standardized incidence rate of the top four cancers with strong evidence for radiation risks between the "plant-vicinity" with those "non-plant-vicinity" groups. All cancer sites, five-leading cancers in Taiwan, and gender-specific cancers were also studied. We also adopted different observation time to compare the incidence rate of cancers between two groups to explore the impact of the observation period. The incidences of leukemia, thyroid, lung, and breast cancer were not significantly different between two groups, but cervix uteri cancer showed higher incidence rates in the plant-vicinity group. The incidence of cervical cancer was not consistently associated with the duration of plant operation, according to a multiyear period comparison. Although there was higher incidence in cervix cancer in the plant-vicinity group, our findings did not provide the crucial evidence that nuclear power plants were the causal factor for some cancers with strong evidence for radiation risks.

  1. Nuclear power plant siting

    Sulkiewicz, M.; Navratil, J.

    The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

  2. Optimization, selection and feasibility study of solar parabolic trough power plants for Algerian conditions

    Boukelia, T.E.; Mecibah, M.S.; Kumar, B.N.; Reddy, K.S.

    2015-01-01

    Highlights: • Evaluation of solar resources in the absence of measured data. • Optimization of 2 PTSTPPs integrated with TES and FBS and using oil and salt as HTFs. • 4E comparative study of the two optimized plants alongside the Andasol 1 plant. • The salt plant resulting as the best one and has been chosen for the viability study. • Tamanrasset is the best location for construction of PTSTPPs. - Abstract: In the present study, optimization of two parabolic trough solar thermal power plants integrated with thermal energy storage (TES), and fuel backup system (FBS) has been performed. The first plant uses Therminol VP-1 as heat transfer fluid in the solar field and the second plant uses molten salt. The optimization is carried out with solar multiple (SM) and full load hours of TES as the parameters, with an objective of minimizing the levelized cost of electricity (LCOE) and maximizing the annual energy yield. A 4E (energy–exergy–environment–economic) comparison of the optimized plants alongside the Andasol 1 as reference plant is studied. The molten salt plant resulting as the best technology, from the optimization and 4E comparative study has been chosen for the viability analysis of ten locations in Algeria with semi-arid and arid climatic conditions. The results indicate that Andasol 1 reference plant has the highest mean annual energy efficiency (17.25%) and exergy efficiency (23.30%). Whereas, the highest capacity factor (54.60%) and power generation (236.90 GW h) are exhibited by the molten salt plant. The molten salt plant has least annual water usage of about 800,482 m 3 , but demands more land for the operation. Nevertheless the oil plant emits the lowest amount of CO 2 gas (less than 40.3 kilo tonnes). From the economic viewpoint, molten salt seems to be the best technology compared to other plants due to its lowest investment cost (less than 360 million dollars) and lower levelized cost of electricity (LCOE) (8.48 ¢/kW h). The

  3. Images of nuclear power plants

    Hashiguchi, Katsuhisa; Misumi, Jyuji; Yamada, Akira; Sakurai, Yukihiro; Seki, Fumiyasu; Shinohara, Hirofumi; Misumi, Emiko; Kinjou, Akira; Kubo, Tomonori.

    1995-01-01

    This study was conducted to check and see, using Hayashi's quantification method III, whether or not the respondents differed in their images of a nuclear power plant, depending on their demographic variables particularly occupations. In our simple tabulation, we compared subject groups of nuclear power plant employees with general citizens, nurses and students in terms of their images of a nuclear power plant. The results were that while the nuclear power plant employees were high in their evaluations of facts about a nuclear power plant and in their positive images of a nuclear power plant, general citizens, nurses and students were overwhelmingly high in their negative images of a nuclear power plant. In our analysis on category score by means of the quantification method III, the first correlation axis was the dimension of 'safety'-'danger' and the second correlation axis was the dimension of 'subjectivity'-'objectivity', and that the first quadrant was the area of 'safety-subjectivity', the second quadrant was the area of 'danger-subjectivity', the third quadrant as the area of 'danger-objectivity', and the forth quadrant was the area of 'safety-objectivity'. In our analysis of sample score, 16 occupation groups was compared. As a result, it was found that the 16 occupation groups' images of a nuclear power plant were, in the order of favorableness, (1) section chiefs in charge, maintenance subsection chiefs, maintenance foremen, (2) field leaders from subcontractors, (3) maintenance section members, operation section members, (4) employees of those subcontractors, (5) general citizens, nurses and students. On the 'safety-danger' dimension, nuclear power plant workers on the one hand and general citizens, nurses and students on the other were clearly divided in terms of their images of a nuclear power plant. Nuclear power plant workers were concentrated in the area of 'safety' and general citizens, nurses and students in the area of 'danger'. (J.P.N.)

  4. A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

    Yang, Y. K.; Jung, Y. D.; Kim, S. Y.

    1991-12-01

    The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system

  5. A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

    Yang, Y K; Jung, Y D; Kim, S Y [Korea Institute of Science and Technology, Seoul (Korea, Republic of)

    1991-12-15

    The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system.

  6. Field-Reversed Configuration Power Plant Critical-Issue Scoping Study

    Santarius, J. F.; Mogahed, E. A.; Emmert, G. A.; Khater, H. Y.; Nguyen, C. N.; Ryzhkov, S. V.; Stubna, M. D.

    2000-03-31

    A team from the Universities of Wisconsin, Washington, and Illinois performed an engineering scoping study of critical issues for field-reversed configuration (FRC) power plants. The key tasks for this research were (1) systems analysis for deuterium-tritium (D-T) FRC fusion power plants, and (2) conceptual design of the blanket and shield module for an FRC fusion core. For the engineering conceptual design of the fusion core, the project team focused on intermediate-term technology. For example, one decision was to use steele structure. The FRC systems analysis led to a fusion power plant with attractive features including modest size, cylindrical symmetry, good thermal efficiency (52%), relatively easy maintenance, and a high ratio of electric power to fusion core mass, indicating that it would have favorable economics.

  7. Field-Reversed Configuration Power Plant Critical-Issue Scoping Study

    Santarius, J. F.; Mogahed, E. A.; Emmert, G. A.; Khater, H. Y.; Nguyen, C. N.; Ryzhkov, S. V.; Stubna, M. D.

    2000-01-01

    A team from the Universities of Wisconsin, Washington, and Illinois performed an engineering scoping study of critical issues for field-reversed configuration (FRC) power plants. The key tasks for this research were (1) systems analysis for deuterium-tritium (D-T) FRC fusion power plants, and (2) conceptual design of the blanket and shield module for an FRC fusion core. For the engineering conceptual design of the fusion core, the project team focused on intermediate-term technology. For example, one decision was to use steele structure. The FRC systems analysis led to a fusion power plant with attractive features including modest size, cylindrical symmetry, good thermal efficiency (52%), relatively easy maintenance, and a high ratio of electric power to fusion core mass, indicating that it would have favorable economics

  8. Study of the Radiological Impact of the Coal Fired Power Plants on the Environment. The As Pontes coal-fired Power Plant

    Cancio, D.; Robles, B.; Mora, J. C.

    2009-01-01

    As part of the Study carried out to determine the radiological impact of the four main Spanish coal-fired power plants, the Study on the As Pontes Coal-Fired Coal Power Plant was finalized. In the Report containing the study are included every measurement performed, as well as the modelling and evaluations carried out in order to assess the radiological impact. The general conclusion obtained is that under a radiological point of view, the impact of this installation on the public and the environment is very small. Also the radiological impact on the workers of the installation was assessed, obtaining too very small increases over the natural background. (Author) 61 refs.

  9. Ageing study of protection automation components of Olkiluoto nuclear power plant

    Simola, K.; Haenninen, S.

    1993-07-01

    A study on ageing of reactor protection system of the Olkiluoto nuclear power plant is described. The objective of the study was to present an ageing analysis approach and apply in to the automation chains of reactor protection system of the Olkiluoto nuclear power plant. The study includes the measuring instrumentation, the protection logics, and the control electronics of some pumps and valves. The analysis is based on the information collected on the structure of the system, environmental conditions and maintenance practices of components, and operating experience. Based on this information, the possible ageing effects of equipment and their safety significance are evaluated. (orig.). (15 refs., 16 figs., 12 tabs.)

  10. A Study on Salt Attack Protection of Structural and Finishing Materials in Power Plant Structures

    Kim, W B; Kweon, K J; Suh, Y P; Nah, H S; Lee, K J; Park, D S; Jo, Y K [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-12-31

    This is a final report written by both KEPRI and KICT as a co-operative research titled {sup A} study on Salt Protection of Structural and Finishings in Power Plant Structures{sup .} This study presented the methods to prevent the chloride-induced corrosion of power plant structures through collection and analysis of research datum relating to design, construction and maintenance for the prevention of structural and finishing materials, thru material performance tests for anti-corrosion under many kinds of chloride-induced corrosion environments. As a result, this study proposed the guidelines for design, construction and maintenance of power plant structures due to chloride-induced corrosion. (author). 257 refs., 111 figs., 86 tabs.

  11. A Study on Salt Attack Protection of Structural and Finishing Materials in Power Plant Structures

    Kim, W.B.; Kweon, K.J.; Suh, Y.P.; Nah, H.S.; Lee, K.J.; Park, D.S.; Jo, Y.K. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1997-12-31

    This is a final report written by both KEPRI and KICT as a co-operative research titled {sup A} study on Salt Protection of Structural and Finishings in Power Plant Structures{sup .} This study presented the methods to prevent the chloride-induced corrosion of power plant structures through collection and analysis of research datum relating to design, construction and maintenance for the prevention of structural and finishing materials, thru material performance tests for anti-corrosion under many kinds of chloride-induced corrosion environments. As a result, this study proposed the guidelines for design, construction and maintenance of power plant structures due to chloride-induced corrosion. (author). 257 refs., 111 figs., 86 tabs.

  12. Advanced Fusion Power Plant Studies. Annual Report for 1999

    Chan, V.S.; Chu, M.S.; Greenfield, C.M.; Kinsey, J.E.

    2000-01-01

    Significant progress in physics understanding of the reversed shear advanced tokamak regime has been made since the last ARIES-RS study was completed in 1996. The 1999 study aimed at updating the physics design of ARIES-RS, which has been renamed ARIES-AT, using the improved understanding achieved in the last few years. The new study focused on: Improvement of beta-limit stability calculations to include important non-ideal effects such as resistive wall modes and neo-classical tearing modes; Use of physics based transport model for internal transport barrier (ITB) formation and sustainment; Comparison of current drive and rotational flow drive using fast wave, electron cyclotron wave and neutral particle beam; Improvement in heat and particle control; Integrated modeling of the optimized scenario with self-consistent current and transport profiles to study the robustness of the bootstrap alignment, ITB sustainment, and stable path to high beta and high bootstrap fraction operation

  13. German risk study on nuclear power plants. Vol. 3

    Albertz, V.; Gueldner, W.; Hoemke, P.; Hoertner, H.; Lindauer, E.; Linden, J. von; Preischl, W.; Reichart, G.; Roehrs, W.

    1980-01-01

    This appendix discusses those studies which were carried out in phase A of the German Risk Study on the following problems: occurrence frequencies of initiating events, evaluation of the reactor pressure vessel, failure rates and failure probabilities for components, probabilities for human error. The appendix describes the general procedure used in determining these parameters. In addition, it gives the individual values used and the sources employed to determine these values. (orig.) [de

  14. A Study on infrared tracing and monitoring of thermal discharge from the power plants

    Choi, Byung Sun; Hong, Wuk Hee; Kim, Yung Bae; Park, Jang Rae; Choi, Yung An; Park, Yung San [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-08-01

    Massive discharge of cooling water from the nuclear power plants as well as many thermal power plants would cause serious environmental problems. Hence, the task of predicting cooling water dispersion areas has enormous importance for better environmental management related with the power plant operation. For the last two decades, extensive field survey and dispersion modeling have been mainly applied to predict thermal discharge dispersion areas. In this study, the method of infrared thermal sensing was tested as a possible means of measuring the affected areas of thermal discharge at the thermal power plant sites. Many IR images obtained by using the terrestrial camera, or by using the airborne scanner, or from the Landsat iv satellite were analyzed from the pc with the IDRISI and resource software and further enhanced with other image analysis technologies. The result of study proved this IR imaging technology to be an potentially cost-effective tool for assessment of water-temperature increase caused by the thermal discharge from the power plants, however, further elaboration of procedure was highly requested. (author). 9 refs., 24 figs.

  15. Life Cycle Assessment of Producing Electricity in Thailand: A Case Study of Natural Gas Power Plant

    Usapein Parnuwat

    2017-01-01

    Full Text Available Environmental impacts from natural gas power plant in Thailand was investigated in this study. The objective was to identify the hotspot of environmental impact from electricity production and the allocation of emissions from power plant was studied. All stressors to environment were collected for annual natural gas power plant operation. The allocation of environmental load between electricity and steam was done by WRI/WBCSD method. Based on the annual power plant operation, the highest of environmental impact was fuel combustion, followed by natural gas extraction, and chemical reagent. After allocation, the result found that 1 kWh of electricity generated 0.425 kgCO2eq and 1 ton of steam generated 225 kgCO2eq. When compared based on 1GJ of energy product, the result showed that the environmental impact of electricity is higher than steam product. To improve the environmental performance, it should be focused on the fuel combustion, for example, increasing the efficiency of gas turbine, and using low sulphur content of natural gas. This result can be used as guideline for stakeholder who engage with the environmental impact from power plant; furthermore, it can be useful for policy maker to understand the allocation method between electricity and steam products.

  16. Stratification studies in components of nuclear power plants

    Randorf, J.A.

    1997-01-01

    The applicability of two stratification criteria during loss-of-coolant (LOCA) conditions was studied. The first criteria was developed for addressing cold water injection-induced stratification. The second criteria applied to downcomer/cold leg junction stratification. Both criteria provided predictions consistent with measured conditions during small break loss-of-coolant tests

  17. Demonstration tokamak power plant

    Abdou, M.; Baker, C.; Brooks, J.; Ehst, D.; Mattas, R.; Smith, D.L.; DeFreece, D.; Morgan, G.D.; Trachsel, C.

    1983-01-01

    A conceptual design for a tokamak demonstration power plant (DEMO) was developed. A large part of the study focused on examining the key issues and identifying the R and D needs for: (1) current drive for steady-state operation, (2) impurity control and exhaust, (3) tritium breeding blanket, and (4) reactor configuration and maintenance. Impurity control and exhaust will not be covered in this paper but is discussed in another paper in these proceedings, entitled Key Issues of FED/INTOR Impurity Control System

  18. Feasibility study on floating nuclear power plant (2). Safety design study of FNPP. Contract research

    Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Masao [Niigata Engineering Co. Ltd., Tokyo (Japan); Nakazawa, Toshio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Sato, Kazuo [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

    2001-02-01

    In the previous report of 'Conceptual Design Study of FNPP (Floating Nuclear Power Plant)', a design study on a concept for FNPP, which is sited off the sea coast on the open sea with water depth of 20m and it is moored on protected sea by the breakwater was conducted and the floating platform guarded by the breakwater was found to be stable enough to install the nuclear power plant from analysis simulating the movement of the platform due to sea wave or wind. In this report, studies on a basic safety design concept of the FNPP, setting natural phenomena for design condition, required safety functions and a review on dynamic analysis of the large floating structure are presented. The studies revealed that the stability of the floating platform is an essential issue for the FNPP soundness, and the design base natural phenomena such as S1 and S2-class storm including S1 and S2-class earthquake should be considered in evaluation of the stability of the floating platform, and it is one of key technical subjects how to set the magnitude of these storm in application of design evaluation on each FNPP case. (J.P.N.)

  19. Nuclear power plant construction

    Lima Moreira, Y.M. de.

    1979-01-01

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.) [pt

  20. Nuclear power plant decommissioning

    Yaziz Yunus

    1986-01-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

  1. Ambient temperature effects on gas turbine power plant: A case study in Iran

    Gorji, M.; Fouladi, F.

    2007-01-01

    Actual thermal efficiency, electric-power output, fuel-air ratio and specific fuel consumption (SFC) vary according to the ambient conditions. The amount of these variations greatly affects those parameters as well as the plant incomes. In this paper the effect of ambient temperature as a seasonal variation on a gas power plant has been numerically studied. For this purpose, the gas turbine model and different climate seasonal variations of Ray in Iran are considered in this study. For the model, by using average monthly temperature data of the region, the different effective parameters were compared to those in standard design conditions. The results show that ambient temperature increase will decrease thermal efficiency, electric-power out put and fuel-air ratio of the gas turbine plant whereas increases the specific fuel consumption

  2. A study on the leak monitoring of boiler tube in power plants

    Lee, Sang Guk

    2002-01-01

    Main equipment of thermal power plant, such as boiler and turbine, are designed and manufactured by domestic techniques. But the special equipments monitoring the operation status of these main facilities are still dependent upon foreign technology. Therefore, so as to develop boiler tube leak detection system, we performed studying on manufacturing, installation in site, Acoustic Emission (AE) signal analysis and discrimination etc. As result of studying on boiler tube leak detection using AE, we conformed that diagnosis for boiler tube and computerized their trend management is possible, and also it is expected to contribute to safe operation of power plant facilities

  3. A Study of KHNP Nuclear Power Plant Technology Level Evaluation

    Yang, Seung Han; Lee, Sung Jin; Kim, Yo Han

    2016-01-01

    KHNP's 2030 mid and long term plan goal in technology field is securing global No. 1 NPP technology level. Quantifying technology level for this purpose, technology level at present should be surveyed. Technology level of South Korea has been surveyed by KISTEP (Korea Institute of S and T Evaluation and Planning) every two year but the technology level of KHNP has not been surveyed by any organization including KHNP itself. Also the size of technology surveyed by KISTEP was too broad to quantifying technology level of KHNP. In this paper, technology level of KHNP and South Korea are presented. In this study, NPP related technologies were divided into Level I and Level II technologies and conducted a survey for each Level II technologies using Delphi questionnaire survey that is widely used in technology level evaluation. The results of technology level and gap will be used from strategic point of view and also as a reference data for technology improvement planning

  4. A Study of KHNP Nuclear Power Plant Technology Level Evaluation

    Yang, Seung Han; Lee, Sung Jin; Kim, Yo Han [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    KHNP's 2030 mid and long term plan goal in technology field is securing global No. 1 NPP technology level. Quantifying technology level for this purpose, technology level at present should be surveyed. Technology level of South Korea has been surveyed by KISTEP (Korea Institute of S and T Evaluation and Planning) every two year but the technology level of KHNP has not been surveyed by any organization including KHNP itself. Also the size of technology surveyed by KISTEP was too broad to quantifying technology level of KHNP. In this paper, technology level of KHNP and South Korea are presented. In this study, NPP related technologies were divided into Level I and Level II technologies and conducted a survey for each Level II technologies using Delphi questionnaire survey that is widely used in technology level evaluation. The results of technology level and gap will be used from strategic point of view and also as a reference data for technology improvement planning.

  5. A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I)

    Kim, W.

    1985-01-01

    The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during perceives and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant * General Requirement. * Principle and Methods of Ultrasonic Test. * Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspire of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huge system, the

  6. AMERICAN ELECTRIC POWER'S CONESVILLE POWER PLANT UNIT NO.5 CO2 CAPTURE RETROFIT STUDY

    Carl R. Bozzuto; Nsakala ya Nsakala; Gregory N. Liljedahl; Mark Palkes; John L. Marion

    2001-06-30

    ALSTOM Power Inc.'s Power Plant Laboratories (ALSTOM) has teamed with American Electric Power (AEP), ABB Lummus Global Inc. (ABB), the US Department of Energy National Energy Technology Laboratory (DOE NETL), and the Ohio Coal Development Office (OCDO) to conduct a comprehensive study evaluating the technical feasibility and economics of alternate CO{sub 2} capture and sequestration technologies applied to an existing US coal-fired electric generation power plant. The motivation for this study was to provide input to potential US electric utility actions concerning GHG emissions reduction. If the US decides to reduce CO{sub 2} emissions, action would need to be taken to address existing power plants. Although fuel switching from coal to natural gas may be one scenario, it will not necessarily be a sufficient measure and some form of CO{sub 2} capture for use or disposal may also be required. The output of this CO{sub 2} capture study will enhance the public's understanding of control options and influence decisions and actions by government, regulators, and power plant owners in considering the costs of reducing greenhouse gas CO{sub 2} emissions. The total work breakdown structure is encompassed within three major reports, namely: (1) Literature Survey, (2) AEP's Conesville Unit No.5 Retrofit Study, and (3) Bench-Scale Testing and CFD Evaluation. The report on the literature survey results was issued earlier by Bozzuto, et al. (2000). Reports entitled ''AEP's Conesville Unit No.5 Retrofit Study'' and ''Bench-Scale Testing and CFD Evaluation'' are provided as companion volumes, denoted Volumes I and II, respectively, of the final report. The work performed, results obtained, and conclusions and recommendations derived therefrom are summarized.

  7. International power plant business

    Grohe, R.

    1986-03-03

    At the Brown Boveri press seminar 'Energy' in Baden-Baden Rainer Grohe, member of the Brown Boveri board, Mannheim, gave a survey of the activities on the international power plant market in recent years. He showed the vacuities which must be taken into account in this sector today. The drastic escalation of demands on power plant suppliers has lead not to a reduction of protagonists but to an increase. (orig.).

  8. German risk study for nuclear power plants. Vol. 5

    Bracht, K.F.; Javeri, V.; Keusenhoff, J.; Meier, S.; Roehrs, W.; Scharfe, A.; Tiltmann, M.; Mayinger, F.

    1980-01-01

    This appendix contains the analyses on core melt accidents carried out for the German risk study. These accidents constitute a major portion of the event sequences relevant to the risk. It deals, in particular, with the processes involved in the reactor core melt, the behaviour of the containment vessel including the possible types of failures, and the consequences of possible steam explosions. The investigations were performed for limiting cases for which a complete failure of the emergency core cooling and residual heat removal system is anticipated. Under these conditions, the reactor core melts down and penetrates the reactor pressure vessel bottom. In the course of the following interaction between core melt and concrete foundation, the melt is assumed to come into contact with the sump water. The evaporation of the sump water leads to an overpressure failure of the containment vessel within approximately one day after accident initiation. A destruction of the containment as a consequence of a steam explosion is considered highly unprobable. (orig.) [de

  9. A study on electric power management for power producer-suppliers utilizing output of megawatt-solar power plants

    Hirotaka Takano

    2016-01-01

    Full Text Available The growth in penetration of photovoltaic generation units (PVs has brought new power management ideas, which achieve more profitable operation, to Power Producer-Suppliers (PPSs. The expected profit for the PPSs will improve if they appropriately operate their controllable generators and sell the generated electricity to contracted customers and Power Exchanges together with the output of Megawatt-Solar Power Plants (MSPPs. Moreover, we can expect that the profitable cooperation between the PPSs and the MSPPs decreases difficulties in the supply-demand balancing operation for the main power grids. However, it is necessary that the PPSs treat the uncertainty in output prediction of PVs carefully. This is because there is a risk for them to pay a heavy imbalance penalty. This paper presents a problem framework and its solution to make the optimal power management plan for the PPSs in consideration with the electricity procurement from the MSPPs. The validity of the authors’ proposal is verified through numerical simulations and discussions of their results.

  10. Offshore atomic power plants

    Anon.

    1975-01-01

    Various merits of offshore atomic power plants are illustrated, and their systems are assessed. The planning of the offshore atomic power plants in USA is reviewed, and the construction costs of the offshore plant in Japan were estimated. Air pollution problem may be solved by the offshore atomic power plants remarkably. Deep water at low temperature may be advantageously used as cooling water for condensers. Marine resources may be bred by building artificial habitats and by providing spring-up equipments. In the case of floating plants, the plant design can be standardized so that the construction costs may be reduced. The offshore plants can be classified into three systems, namely artificial island system, floating system and sea bottom-based system. The island system may be realized with the present level of civil engineering, but requires the development of technology for the resistance of base against earthquake and its calculation means. The floating system may be constructed with conventional power plant engineering and shipbuilding engineering, but the aseismatic stability of breakwater may be a problem to be solved. Deep water floating system and deep water submerging system are conceivable, but its realization may be difficult. The sea bottom-based system with large caissons can be realized by the present civil engineering, but the construction of the caissons, stability against earthquake and resistance to waves may be problems to be solved. The technical prediction and assessment of new plant sites for nuclear power plants have been reported by Science and Technology Agency in 1974. The construction costs of an offshore plant has been estimated by the Ministry of International Trade and Industry to be yen71,026/kW as of 1985. (Iwakiri, K.)

  11. Target study of heat supply from Northern Moravia nuclear power plant

    Pospisil, V.

    The construction is envisaged in Northern Moravia of a nuclear power plant near Blahutovice in the Novy Jicin district. Heat produced by the nuclear power plant will only be used for district heating; process heat will be supplied from local steam sources. An example is discussed of the Prerov locality which currently is supplied from the Prerov heating and power plant (230 MW), a heating plant (36 MW) and from local sources (15 NW). The study estimates that a thermal power of 430 MW will be required at a time of the start of heat supplies from the nuclear power plant. All heat supply pipelines will be designed as a two-tube system divided into sections with section pipe fittings. The number and location of pipe fittings will be selected depending on the terrain configuration. Water of the maximum outlet temperature of 150 degC will be used as a coolant. The control of the system for Northern Moravia is briefly described. (J.P.)

  12. Power plants 2010. Lectures

    2010-01-01

    The proceedings include the following lectures: Facing the challenges - new structures for electricity production. Renewable energies in Europe - chances and challenges. Nuclear outlook in the UK. Sustainable energy for Europe. Requirements of the market and the grid operator at the electricity production companies. Perspectives for the future energy production. Pumped storage plants - status and perspectives. Nuclear power/renewable energies -partners or opponents? New fossil fired power stations in Europe - status and perspectives. Nuclear energy: outlook for new build and lifetime extension in Europe. Biomass in the future European energy market - experiences for dong energy. Meeting the EU 20:20 renewable energy targets: the offshore challenges. DESERTEC: sustainable electricity for Europe, Middle East and North Africa. New power plants in Europe - a challenge for project and quality management. Consideration of safely in new build activities of power plants. Challenges to an integrated development in Maasvlakte, Netherlands. Power enhancement in EnBW power plants. Operational experiences of CCS pilot plants worldwide. Two years of operational experiences with Vattenfall's oxyfuel pilot plant. Pre-conditions for CCS. Storage technologies for a volatile generation. Overview: new generation of gas turbines.

  13. Study of flue gas condensing for biofuel fired heat and power plants; Studie av roekgaskondensering foer biobraensleeldade kraftvaermeanlaeggningar

    Axby, Fredrik; Gustafsson, J O; Nystroem, Johan; Johansson, Kent

    2000-11-01

    This report considers questions regarding flue gas condensing plants connected to bio-fuelled heat and power plants. The report consists of two parts, one where nine existing plants are described regarding technical issues and regarding the experience from the different plants. Part two is a theoretical study where heat balance calculations are made to show the technical and economical performance in different plant configurations and operating conditions. Initially the different parts in the flue gas condensing plant are described. Tube, plate and scrubber condensers are described briefly. The different types of humidifiers are also described, rotor, cross-stream plate heat exchanger and scrubber. Nine flue gas-condensing plants have been visited. The plants where chosen considering it should be bio-fuel fired plant primarily heat and power plants. Furthermore we tried to get a good dissemination considering plant configuration, supplier, geographical position, operating situation and plant size. The description of the different plants focuses on the flue gas condenser and the belonging components. The fuel, flue gas and condensate composition is described as well as which materials are used in the different parts of the plant. The experience from operating the plants and the reasons of why they decided to chose the actual condenser supplier are reported.

  14. Nuclear closed-cycle gas turbine (HTGR-GT): dry cooled commercial power plant studies

    McDonald, C.F.; Boland, C.R.

    1979-11-01

    Combining the modern and proven power conversion system of the closed-cycle gas turbine (CCGT) with an advanced high-temperature gas-cooled reactor (HTGR) results in a power plant well suited to projected utility needs into the 21st century. The gas turbine HTGR (HTGR-GT) power plant benefits are consistent with national energy goals, and the high power conversion efficiency potential satisfies increasingly important resource conservation demands. Established technology bases for the HTGR-GT are outlined, together with the extensive design and development program necessary to commercialize the nuclear CCGT plant for utility service in the 1990s. This paper outlines the most recent design studies by General Atomic for a dry-cooled commercial plant of 800 to 1200 MW(e) power, based on both non-intercooled and intercooled cycles, and discusses various primary system aspects. Details are given of the reactor turbine system (RTS) and on integrating the major power conversion components in the prestressed concrete reactor vessel

  15. Power plant at sea

    Roggen, M.

    2000-01-01

    Drilling platforms are rather inefficient when it comes to their own power supply. In view of ecotax and their environmental image, the offshore industry particularly the Norwegians is highly committed to changing this situation. An efficient power plant, specially designed for the offshore industry, might just prove to be the answer to their prayers

  16. A Study on Evaluation Issues of Real-Time Operating System in Nuclear Power Plants

    Kim, Y. M.; Jeong, C. H.; Koh, J. S. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2006-07-01

    Control applications such as aircraft, robotics and nuclear power plant have to maintain a very high level of safety, typically defined as the avoidance of unplanned events resulting in hazard. These applications usually operate with hard real-time operating system (RTOS). In this case, hard RTOS software should be reliable and safe. RTOS used in safety-critical I and C system is the base software for the purpose of satisfying the real-time constraints. So, careful evaluation of its safety and functionality is very important. In this paper, we present the case study for RTOSs used in real nuclear power plants (NPP), and suggest the evaluation approach for the RTOS.

  17. Perceived nuclear risk, organizational commitment, and appraisals of management: A study of nuclear power plant personnel

    Kivimaeki, M.; Kalimo, R.; Salminen, S.

    1995-01-01

    This study examined to what extent nuclear risk perceptions, organizational commitment (OC), and appraisals of management are associated with each other among nuclear power plant personnel. The sample consisted of 428 nuclear power plant workers who completed a questionnaire at their workplace. Perceived nuclear risk and OC were most closely related to the appraisals of the top management of the organization. As the trust in and satisfaction with the top management increased, perceived nuclear safety and acceptance of the organizational goals and values heightened. This result is discussed in the context of industrial safety management. 29 refs., 2 tabs

  18. A Study on Evaluation Issues of Real-Time Operating System in Nuclear Power Plants

    Kim, Y. M.; Jeong, C. H.; Koh, J. S.

    2006-01-01

    Control applications such as aircraft, robotics and nuclear power plant have to maintain a very high level of safety, typically defined as the avoidance of unplanned events resulting in hazard. These applications usually operate with hard real-time operating system (RTOS). In this case, hard RTOS software should be reliable and safe. RTOS used in safety-critical I and C system is the base software for the purpose of satisfying the real-time constraints. So, careful evaluation of its safety and functionality is very important. In this paper, we present the case study for RTOSs used in real nuclear power plants (NPP), and suggest the evaluation approach for the RTOS

  19. Identification of seismically risk-sensitive systems and components in nuclear power plants: feasibility study

    Azarm, M.; Boccio, J.; Farahzad, P.

    1983-06-01

    An approach for the identification of risk-sensitive components in a nuclear power plant during and after a seismic event is described. Application of the methodology to two hypothetical power plants - a Boiling Water Reactor and a Pressurized Water Reactor - are presented and the results are given in tabular and graphical form. Conclusions drawn and lessons learned through the course of this study, based on the relative importance of various accident scenarios and sensitivity analyses, are discussed. In addition, the areas that may need further investigation are identified

  20. Nuclear power plants maintenance

    Anon.

    1988-01-01

    Nuclear power plants maintenance now appears as an important factor contributing to the competitivity of nuclea energy. The articles published in this issue describe the way maintenance has been organized in France and how it led to an actual industrial activity developing and providing products and services. An information note about Georges Besse uranium enrichment plant (Eurodif) recalls that maintenance has become a main data not only for power plants but for all nuclear industry installations. (The second part of this dossier will be published in the next issue: vol. 1 January-February 1989) [fr

  1. Nuclear power plant outages

    1998-01-01

    The Finnish Radiation and Nuclear Safety Authority (STUK) controls nuclear power plant safety in Finland. In addition to controlling the design, construction and operation of nuclear power plants, STUK also controls refuelling and repair outages at the plants. According to section 9 of the Nuclear Energy Act (990/87), it shall be the licence-holder's obligation to ensure the safety of the use of nuclear energy. Requirements applicable to the licence-holder as regards the assurance of outage safety are presented in this guide. STUK's regulatory control activities pertaining to outages are also described

  2. Exergetic and Parametric Study of a Solar Aided Coal-Fired Power Plant

    Eric Hu

    2013-03-01

    Full Text Available A solar-aided coal-fired power plant realizes the integration of a fossil fuel (coal or gas and clean energy (solar. In this paper, a conventional 600 MW coal-fired power plant and a 600 MW solar-aided coal-fired power plant have been taken as the study case to understand the merits of solar-aided power generation (SAPG technology. The plants in the case study have been analyzed by using the First and Second Laws of Thermodynamics principles. The solar irradiation and load ratio have been considered in the analysis. We conclude that if the solar irradiation was 925 W/m2 and load ratio of the SAPG plant was 100%, the exergy efficiency would be 44.54% and the energy efficiency of the plant (46.35%. It was found that in the SAPG plant the largest exergy loss was from the boiler, which accounted for about 76.74% of the total loss. When the load ratio of the unit remains at 100%, and the solar irradiation varies from 500 W/m2 to 1,100 W/m2, the coal savings would be in the range of 8.6 g/kWh to 15.8 g/kWh. If the solar irradiation were kept at 925 W/m2 while the load ratio of the plant changed from 30% to 100%, the coal savings could be in the range of 11.99 g/kWh to 13.75 g/kWh.

  3. Nuclear Power Plants (Rev.)

    Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

    1973-01-01

    Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

  4. LNG plant combined with power plant

    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.

  5. LNG plant combined with power plant

    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

  6. Inertial fusion commercial power plants

    Logan, B.G.

    1994-01-01

    This presentation discusses the motivation for inertial fusion energy, a brief synopsis of five recently-completed inertial fusion power plant designs, some general conclusions drawn from these studies, and an example of an IFE hydrogen synfuel plant to suggest that future fusion studies consider broadening fusion use to low-emission fuels production as well as electricity

  7. Nuclear Power Plant 1996

    1997-01-01

    Again this year, our magazine presents the details of the conference on Spanish nuclear power plant operation held in February and that was devoted to 1996 operating results. The Protocol for Establishment of a New Electrical Sector Regulation that was signed last December will undoubtedly represent a new challenge for the nuclear industry. By clearing stating that current standards of quality and safety should be maintained or even increased if possible, the Protocol will force the Sector to improve its productivity, which is already high as demonstrated by the results of the last few years described during this conference and by recent sectorial economic studies. Generation of a nuclear kWh that can compete with other types of power plants is the new challenge for the Sector's professionals, who do not fear the new liberalization policies and approaching competition. Lower inflation and the resulting lower interest rates, apart from being representative indices of our economy's marked improvement, will be very helpful in facing this challenge. (Author)

  8. Next Generation Geothermal Power Plants

    Brugman, John; Hattar, Mai; Nichols, Kenneth; Esaki, Yuri

    1995-09-01

    A number of current and prospective power plant concepts were investigated to evaluate their potential to serve as the basis of the next generation geothermal power plant (NGGPP). The NGGPP has been envisaged as a power plant that would be more cost competitive (than current geothermal power plants) with fossil fuel power plants, would efficiently use resources and mitigate the risk of reservoir under-performance, and minimize or eliminate emission of pollutants and consumption of surface and ground water. Power plant concepts were analyzed using resource characteristics at ten different geothermal sites located in the western United States. Concepts were developed into viable power plant processes, capital costs were estimated and levelized busbar costs determined. Thus, the study results should be considered as useful indicators of the commercial viability of the various power plants concepts that were investigated. Broadly, the different power plant concepts that were analyzed in this study fall into the following categories: commercial binary and flash plants, advanced binary plants, advanced flash plants, flash/binary hybrid plants, and fossil/geothed hybrid plants. Commercial binary plants were evaluated using commercial isobutane as a working fluid; both air-cooling and water-cooling were considered. Advanced binary concepts included cycles using synchronous turbine-generators, cycles with metastable expansion, and cycles utilizing mixtures as working fluids. Dual flash steam plants were used as the model for the commercial flash cycle. The following advanced flash concepts were examined: dual flash with rotary separator turbine, dual flash with steam reheater, dual flash with hot water turbine, and subatmospheric flash. Both dual flash and binary cycles were combined with other cycles to develop a number of hybrid cycles: dual flash binary bottoming cycle, dual flash backpressure turbine binary cycle, dual flash gas turbine cycle, and binary gas turbine

  9. A study on the boiler efficiency influenced by the boiler operation parameter in fossil power plant

    Kwon, Y. S.; Suh, J. S.

    2002-01-01

    The main reason to analyze the boiler operation parameter in fossil power plant is to increase boiler high efficiency and energy saving movement in the government. This study intends to have trend and analyze the boiler efficiency influenced by the boiler parameter in sub-critical and super-critical type boiler

  10. Detailed Equivalent VSC-HVDC Modelling for Time Domain Harmonic Stability Studies in Wind Power Plants

    Glasdam, Jakob Bærholm; Bak, Claus Leth; Kocewiak, Lukasz Hubert

    2018-01-01

    system with 201 voltage levels, without loss of accuracy compared to conventional modelling of the converter. Harmonic stability is a core concern for both existing and future offshore wind power plants (OWPPs). A harmonic stability study will be undertaken with focus on the number of wind turbine...

  11. Hydroelectric power plant Irape - viability studies; Usina hidroeletrica Irape - estudos de viabilidade

    Serran, F.P.; Assumpcao, M.G.

    1994-06-01

    The socio-environmental analysis of the feasibility studies from Irape Hydroelectric Power Plant in Minas Gerais State-Brazil was described including three main questions: the regional insertion mentioning the social conflicts, the social communication program and the basic strategic; the reduction of water volume downstream; the development of programs on the Basic Project Stage.

  12. Licensing method for new nuclear power plant: A study on decision making modeling

    Ramli, N; Ohaga, E. O.; Jung, J. C.

    2012-01-01

    This work provides a study on decision making modeling for a licensing method of a new nuclear power plant. SWOT analysis provides the licensing alternatives attributes, then the expectation from either COL or two step licensing method is decided by inputting the output from the Hurwitz mathematical model. From the analysis, COL shows the best candidate for both optimistic and pessimistic conditions

  13. Licensing method for new nuclear power plant: A study on decision making modeling

    Ramli, N; Ohaga, E. O.; Jung, J. C. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2012-10-15

    This work provides a study on decision making modeling for a licensing method of a new nuclear power plant. SWOT analysis provides the licensing alternatives attributes, then the expectation from either COL or two step licensing method is decided by inputting the output from the Hurwitz mathematical model. From the analysis, COL shows the best candidate for both optimistic and pessimistic conditions.

  14. Comparative study T-type and I-type layout of PWR nuclear power plants

    Eko Rudi Iswanto and Siti Alimah

    2010-01-01

    Determining plant layout is one of the five major stages during the life time of a nuclear power plant. Some important factors that affect in the selecting of plant layout are availability of infrastructure, economic aspects, social aspects, public and environment safety, and also easy to do. Another factor to be considered is requirements as seismic design, which refers to the principles of good security workers, communities and the environment of radiological risks. There are many layout types of nuclear power plant, two of them are T-type layout and I-type layout. Each type of the plant layout has advantage and disadvantage, therefore this study is to understand them. Good layout is able to provide a high level of security against earthquakes. In term of earthquake design, I-type layout has a higher security level than T-type layout. Therefore, I-type layout can be a good choice for PWR nuclear power plants 1000 MWe that will be built in Indonesia. (author)

  15. Update on the EPRI power generation risk-based inservice inspection pilot plant studies

    Gosselin, S.R.

    1997-01-01

    The scope for ASME Section XI ISI programs is largely based on deterministic results contained in design stress reports. These reports are normally very conservative and may not be an accurate representation of failure potential. Service experience has shown that failures are due to either corrosion or fatigue and typically occur in areas not included in the plant's ISI program. Consequently, nuclear plants are devoting significant resources to inspection programs that provide minimum benefit. As an alternative, significant industry attention has been devoted to the application of risked-based selection criteria in order to determine the scope of inservice inspection (ISI) programs at nuclear power plants. Preliminary EPRI studies indicate that the application of these techniques will allow operating nuclear plants to reduce the examination scope of current ISI programs by as much as 60 to 80%, significantly reduce costs, and continue to maintain high nuclear plant safety standards

  16. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2001-01-01

    Fundamental concepts on the life extension of the nuclear power plant and decommissioning optimization were established from the domestic abroad information and case analyses. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the standard of the decommissioning(decontamination dismantling) regulation. Moreover, basics were set for the decommissioning of domestic nuclear power plants and research reactors from the analyses on the decommissioning technology and precedence.

  17. Evaluation of Power Generation Efficiency of Cascade Hydropower Plants: A Case Study

    Jiahua Wei

    2013-02-01

    Full Text Available Effective utilization of scarce water resources has presented a significant challenge to respond to the needs created by rapid economic growth in China. In this study, the efficiency of the joint operation of the Three Gorges and Gezhouba cascade hydropower plants in terms of power generation was evaluated on the basis of a precise simulation-optimization technique. The joint operation conditions of the Three Gorges and Gezhouba hydropower plants between 2004 and 2010 were utilized in this research in order to investigate the major factors that could affect power output of the cascade complex. The results showed that the current power output of the Three Gorges and Gezhouba cascade complex had already reached around 90% of the maximum theoretical value. Compared to other influencing factors evaluated in this study, the accuracy of hydrological forecasts and flood control levels can have significant impact on the power generating efficiency, whereas the navigation has a minor influence. This research provides a solid quantitative-based methodology to assess the operation efficiency of cascade hydropower plants, and more importantly, proposes potential methods that could improve the operation efficiency of cascade hydropower plants.

  18. Study on nuclear power plant project construction and management mode in China

    Wang Kai; Chen Lian

    2009-01-01

    Project management mode plays a key role in project construction, especially in nuclear power field. From the aspects of right, responsibility and benefit, this paper discussed the differences among the common used project management modes. Also the main kinds of the construction management modes used in China's nuclear power plants were summarized. At last, considering the experience of Ningde nuclear power plant, this paper put forward several perspectives about the selection of project management mode in nuclear power plant construction. (authors)

  19. Assessing power plant impacts on fish populations at Northeast Utilities sites: winter flounder studies at Millstone Nuclear Power Station

    Lorda, E.; Danila, D.J.; Miller, J.D.; Bireley, L.E.; Jacobsen, P.M.

    1987-01-01

    An historical view is presented of the various impact assessment approaches used to study the winter flounder, including efforts to identify and quantify compensation and to model its population dynamics. This review illustrates the need for unbiased estimates of basic life history parameters and power plant related mortalities if compensatory mechanisms are to be understood and if impact assessments are to be meaningful. 67 references, 19 figures, 10 tables

  20. Study Improving Performance of Centrifugal Compressor In Paiton Coal Fired Power Plant Unit 1 And 2

    Kusuma, Yuriadi; Permana, Dadang S.

    2018-03-01

    The compressed air system becomes part of a very important utility system in a Plant, including the Steam Power Plant. In PLN’S coal fired power plant, Paiton units 1 and 2, there are four Centrifugal air compressor types, which produce compressed air as much as 5.652 cfm and with electric power capacity of 1200 kW. Electricity consumption to operate centrifugal compressor is 7.104.117 kWh per year. This study aims to measure the performance of Centrifugal Compressors operating in Paiton’s coal fired power plant units 1 and 2. Performance Compressor is expressed by Specific Power Consumption (SPC) in kW/100 cfm. For this purpose, we measure the compressed air flow rate generated by each compressor and the power consumed by each compressor. The result is as follows Air Compressor SAC 2B : 15.1 kW/100 cfm, Air Compressor SAC 1B : 15.31 kW/100 cfm,Air Compressor SAC 1A : 16.3 kW/100 cfm and air Compressor SAC 2C : 18.19 kW/100 cfm. From the measurement result, air compressor SAC 2B has the best performance that is 15.1 kW / 100 cfm. In this study we analyze efforts to improve the performance of other compressors to at least match the performance of the SAC 2B air compressor. By increasing the Specific Power Consumption from others Compressor, it will get energy saving up to 284,165 kWh per year.

  1. Comparative study of radiological impact of nuclear power plant and coal-fired power plant: estimation of radiation dose to public from nuclear power plant and coal-fired power plant generation

    Umbara, Heru; Yatim, Sofyan

    1998-01-01

    Radiation impact assessment of Nuclear Power Plant and Coal-Fired Power Plant in Muria Penninsula was carried out. The computation of radionuclide releases to the atmosphere subjects to gaussian plume model, on the other hand, the radionuclide transfer model between environmental compartment (pathway) follow concentration factor methods. Both models are compiled in GENII-The Hanford Environmental Radiation Dosimetry Software System, which is used in the assessment. Most of all input data for GENII package are site specific, such as meteorological data, stack flow, stack height, population, local consumption except the transfer factor data are taken from the GENII package. The results show that during operation of NPP the maximal exposed individual received annual effective dose 150 nSv at 300 -700 m from the site toward east otherwise in operation of CPP the maximal exposed individual received annual effective dose 410 nSv in the same distance and direction. Both results of the maximal exposed individual received annual effective dose about 0,003 % and 0,008 % of whole body annual dose limit for members of public for NPP and CPP. (author)

  2. Wind power plant

    Caneghem, A.E. von

    1975-07-24

    The invention applies to a wind power plant in which the wind is used to drive windmills. The plant consists basically of a vertical tube with a lateral wind entrance opening with windmill on its lower end. On its upper end, the tube carries a nozzle-like top which increases the wind entering the tube by pressure decrease. The wind is thus made suitable for higher outputs. The invention is illustrated by constructional examples.

  3. Benchmarking Nuclear Power Plants

    Jakic, I.

    2016-01-01

    One of the main tasks an owner have is to keep its business competitive on the market while delivering its product. Being owner of nuclear power plant bear the same (or even more complex and stern) responsibility due to safety risks and costs. In the past, nuclear power plant managements could (partly) ignore profit or it was simply expected and to some degree assured through the various regulatory processes governing electricity rate design. It is obvious now that, with the deregulation, utility privatization and competitive electricity market, key measure of success used at nuclear power plants must include traditional metrics of successful business (return on investment, earnings and revenue generation) as well as those of plant performance, safety and reliability. In order to analyze business performance of (specific) nuclear power plant, benchmarking, as one of the well-established concept and usual method was used. Domain was conservatively designed, with well-adjusted framework, but results have still limited application due to many differences, gaps and uncertainties. (author).

  4. Nuclear power plant control room task analysis. Pilot study for pressurized water reactors

    Barks, D.B.; Kozinsky, E.J.; Eckel, S.

    1982-05-01

    The purposes of this nuclear plant task analysis pilot study: to demonstrate the use of task analysis techniques on selected abnormal or emergency operation events in a nuclear power plant; to evaluate the use of simulator data obtained from an automated Performance Measurement System to supplement and validate data obtained by traditional task analysis methods; and to demonstrate sample applications of task analysis data to address questions pertinent to nuclear power plant operational safety: control room layout, staffing and training requirements, operating procedures, interpersonal communications, and job performance aids. Five data sources were investigated to provide information for a task analysis. These sources were (1) written operating procedures (event-based); (2) interviews with subject matter experts (the control room operators); (3) videotapes of the control room operators (senior reactor operators and reactor operators) while responding to each event in a simulator; (4) walk-/talk-throughs conducted by control room operators for each event; and (5) simulator data from the PMS

  5. The part played by applied geology in nuclear power plant site studies

    Giafferi, J.L.

    1994-01-01

    Site-related geological problems are one of the constraints affecting the environment of nuclear power plants. The natural features (soil and subsoil) at the nuclear power plant site affect numerous factors in the design, construction and operation of the civil engineering structures. The site geological criteria are not solely restricted to the soil as a static support for the structures. Earth tremors in France are of moderate intensity but the likelihood of their occurrence must nevertheless be taken into account for each site. Studies must concern the geological and seismic features of the region as well as the soil and subsoil configurations and composition in the immediate vicinity of the site in order to determine the physical characteristics of the earthquakes so that the safety of the plant can be guaranteed; in many cases, water tables have also to be taken into consideration. Geologic survey techniques are discussed. 13 figs., 7 refs

  6. The study of atmospheric dispersion of radionuclide near nuclear power plant using CFD approach

    Nagrale, Dhanesh B.; Bera, Subrata; Deo, Anuj K.; Gaikwad, Avinash J.

    2015-01-01

    Most of the studies on atmospheric dispersion of radioactive material released from nuclear power plants are based on Gaussian plume models which fail to take account turbulence generated. The Fire Dynamic Simulator (FDS) code is one such flow model that uses a form of Navier-Stokes equation for low mach number applications. In the 0-2 km range near nuclear power plant, mainly near the source of emission of radionuclides, obstructions like natural draft cooling towers, plant building and structures are located. The stability class 'F' conditions and temperature of surrounding atmosphere, 15°C are considered in analysis. Main constituents of radionuclides released from stack mainly xenon, krypton. Two cases are carried out a) dispersion of gases without obstruction of cooling tower and b) dispersion of gases with obstruction of cooling tower. It is observed that mass fraction of radionuclides near the cooling tower ground increased to certain extent due to obstruction and wake effect. (author)

  7. Wind power plant

    Kling, A

    1977-01-13

    The wind power plant described has at least one rotor which is coupled to an electricity generator. The systems are fixed to a suspended body so that it is possible to set up the wind power plant at greater height where one can expect stronger and more uniform winds. The anchoring on the ground or on a floating body is done by mooring cables which can simultaneously have the function of an electric cable. The whole system can be steered by fins. The rotor system itself consists of at least one pair of contrarotating, momentum balanced rotors.

  8. Ardennes nuclear power plant

    1974-12-01

    The SENA nuclear power plant continued to operate, as before, at authorized rated power, namely 905MWth during the first half year and 950MWth during the second half year. Net energy production:2028GWh; hours phased to the line: 7534H; availability factor: 84%; utilization factor: 84%; total shutdowns:19; number of scrams:10; cost per KWh: 4,35 French centimes. Overall, the plant is performing very satisfactory. Over the last three years net production has been 5900GWh, corresponding to in average utilization factor of 83%

  9. Nuclear power plant

    Orlov, V.V.; Rineisky, A.A.

    1975-01-01

    The invention is aimed at designing a nuclear power plant with a heat transfer system which permits an accelerated fuel regeneration maintaining relatively high initial steam values and efficiency of the steam power circuit. In case of a plant with three circuits the secondary cooling circuit includes a steam generator with preheater, evaporator, steam superheater and intermediate steam superheater. At the heat supply side the latter is connected with its inlet to the outlet of the evaporator and with its outlet to the low-temperature side of the secondary circuit

  10. TAPCHAN Wave Power Plants

    1983-10-01

    The Tapered Channel Wave Power Plant (TAPCHAN) is based on a new method for wave energy conversion. The principle of operation can be explained by dividing the system into the following four sub-systems: Firstly, a collector which is designed to concentrate the water energy and optimize collection efficiency for a range of frequencies and directions. Secondly, the energy converter, in which the energy of the collected waves is transformed into potential energy in an on-shore water reservoir. This is the unique part of the power plant. It consists of a gradually narrowing channel with wall heights equal to the filling level of the reservoir (typical heights 3-7 m). The waves enter the wide end of the channel and as they propagate down the narrowing channel, the wave height is amplified until the wavecrests spill over the walls. Thirdly, a reservoir which provides a stable water supply for the turbines. Finally, the hydroelectric power plant, where well established techniques are used for the generation of electric power. The water turbine driving the electric generator is of a low head type, such as a Kaplan or a tubular turbine. It must be designed for salt water operation and should have good regulation capabilities. Power plants based on the principle described, are now offered on a commercial basis.

  11. Study on the improvement of working environment at night in maintenance works at nuclear power plants

    Hiramoto, Mitsuru; Kotani, Fumio

    2000-01-01

    At the maintenance work site in nuclear power plants, due to the shortening (reduction of a regular inspection period) of the regular inspection period, the tendency toward working on around-the-clock basis has increased; thus, nighttime work is on the rise. Based upon research both locally and internationally, as well as examples of measures against such a tendency and the results of on-site surveys of the environment surrounding maintenance works at nuclear power plants, the author comprehensively studied the effects of nighttime work on workers, the measures to cope with the situation, and how a working environment for nighttime work should be. Based on the results, the authors made a guidebook for nighttime maintenance work at nuclear power plants. This guidebook, which deals with the subject of nighttime maintenance work at nuclear power plants, is quite unique in the world. It is expected that by using this guidebook, the quality of nighttime maintenance work and the levels of techniques/skills would be enhanced and maintained, and the safety of workers would be ensured, promoting considerably thus the establishment of a comfortable workplace. (author)

  12. Study on the improvement of working environment at night in maintenance works at nuclear power plants

    Hiramoto, Mitsuru; Kotani, Fumio [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

    2000-09-01

    At the maintenance work site in nuclear power plants, due to the shortening (reduction of a regular inspection period) of the regular inspection period, the tendency toward working on around-the-clock basis has increased; thus, nighttime work is on the rise. Based upon research both locally and internationally, as well as examples of measures against such a tendency and the results of on-site surveys of the environment surrounding maintenance works at nuclear power plants, the author comprehensively studied the effects of nighttime work on workers, the measures to cope with the situation, and how a working environment for nighttime work should be. Based on the results, the authors made a guidebook for nighttime maintenance work at nuclear power plants. This guidebook, which deals with the subject of nighttime maintenance work at nuclear power plants, is quite unique in the world. It is expected that by using this guidebook, the quality of nighttime maintenance work and the levels of techniques/skills would be enhanced and maintained, and the safety of workers would be ensured, promoting considerably thus the establishment of a comfortable workplace. (author)

  13. Opportunity study and a business plan for a wind power plant

    Nikolov, Marjan; Naumov, Risto

    2006-01-01

    This paper provides illustration of opportunity study and a business plan for utilizing the wind renewable resource for electricity production in Macedonia. The study is prepared under UNIDO recommendations for feasibility studies (see [1]) and following the IAS, by Marjan Nikolov and Risto Naumov. This is a project simulation for a small wind farm comprising 3 power plant units. We use price list from 'Proven Engineering Products Ltd' UK.

  14. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1990-12-15

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea.

  15. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil

    1990-12-01

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea

  16. A study of air-operated valves in U.S. nuclear power plants

    Rothberg, O. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Khericha, S. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Watkins, J. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Holbrook, M. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States)

    2000-02-01

    A study of air-operated valves in nuclear power plant applications was conducted for the NRC Office of Research (the project was initiated by NRC/AEOD). The results of the study were based on visits to seven nuclear power plant sites, literature studies, and examinations of event records in databases available to the NRC. The purpose is to provide information to the NRC staff concerning capabilities and performance of air-operated valves (AOVs). Descriptions of air systems and AOVs were studied along with the support systems and equipment. Systems and equipment that contain AOVs and SOVs were studied to determine their dependencies. Applications of AOVs and SOVs were listed along with current NRC requirements.

  17. A study of air-operated valves in U.S. nuclear power plants

    Rothberg, O.; Khericha, S.; Watkins, J.; Holbrook, M.

    2000-01-01

    A study of air-operated valves in nuclear power plant applications was conducted for the NRC Office of Research (the project was initiated by NRC/AEOD). The results of the study were based on visits to seven nuclear power plant sites, literature studies, and examinations of event records in databases available to the NRC. The purpose is to provide information to the NRC staff concerning capabilities and performance of air-operated valves (AOVs). Descriptions of air systems and AOVs were studied along with the support systems and equipment. Systems and equipment that contain AOVs and SOVs were studied to determine their dependencies. Applications of AOVs and SOVs were listed along with current NRC requirements.

  18. Site and feasibility studies of a first nuclear power plant in Morocco

    Righi, M.

    1988-11-01

    Basing on the estimated studies related to the evaluation of future needs of electrical energy, the launching of a nuclear power program in Morocco is confirmed necessary. A complete study of sites and feasibility has been carried out. Taking into account the site selection factors two sites: BIR ELHAR and SIDI BOULBRA have been kept as candidate sites. The evaluation of seismic and geotechnical risks of the power plant impact on the environment and risks related to human activities has led to privilege the SIDI BOULBRA site. The studies for confirming this site are summarized. 4 figs. (F.M.)

  19. Conceptual engineering design study of thermionic topping of fossil power plants

    1978-02-15

    Primary objectives of this study are to investigate alternative design concepts of thermal coupling of thermionic energy converters (TECs) to the steam cycle and the mechanical and electrical aspects of integrating TEC design into the steam power station. The specific tasks include: (1) evaluate design concepts of TEC topping of solvent refined liquified coal-fired steam power plants, with main emphasis devoted to thermal, mechanical, and electrical design aspects. (2) Develop preliminary conceptual design of a modular TEC assembly. (3) Develop preliminary cost estimates of the design modification to a liquified coal-fired steam power plant with TEC topping. (4) Provide support to Thermo Electron Corporation in planning TEC hardware testing. Results are presented in detail.

  20. Case study: Proposed application of project management techniques for construction of nuclear power plant in Malaysia

    Syahirah Abdul Rahman; Phongsakorn Prak Tom; Wan Abd Hadi Wan Abu Bakar; Shaharum Ramli

    2010-01-01

    This study discusses the techniques of project management for the construction of nuclear power plants that can be used in Malaysia. Nuclear power reactors are expected to apply is the categories of Gen III + reactor where it is safer and more modern than the first generation of reactors built in the 1970s. The objective of this study is that the construction of this reactor to be completed by the stipulated time and not exceed the cost estimates. In addition, project management is also able to meet all the specifications and achieve the quality standard. In this study, the techniques used in project management to ensure the success of construction projects of nuclear power plants are a Gantt Chart, CPM/ PERT and Microsoft Project. From the study, found that these techniques can assist in facilitating the management of the project for the construction of nuclear power plants to ensure that the estimated time and cost can be managed more effectively as well as quality of care. (author)

  1. Validation of a methodology for the study of generation cost of electric power for nuclear power plants

    Ortega C, R.F.; Martin del Campo M, C.

    2004-01-01

    It was developed a model for the calculation of costs of electric generation of nuclear plants. The developed pattern was validated with the one used by the United States Council for Energy Awareness (USCEA) and the Electric Power Research Institute (EPRI), in studies of comparison of alternatives for electric generation of nuclear plants and fossil plants with base of gas and of coal in the United States described in the guides calls Technical Assessment Guides of EPRI. They are mentioned in qualitative form some changes in the technology of nucleo electric generation that could be included in the annual publication of Costs and Parameters of Reference for the Formulation of Projects of Investment in the Electric Sector of the Federal Commission of Electricity. These changes are in relation to the advances in the technology, in the licensing, in the construction and in the operation of the reactors called advanced as the A BWR built recently in Japan. (Author)

  2. The purpose and organisation of reliability and risk assessment studies for power plant in operation

    Ohlmeier, H.

    1989-01-01

    Upon recommendation of the Reaktorsicherheitskommission RSK, specific, probabilistic safety analyses have to be made within the next few years for every nuclear power plant in operation. The paper deals with the activities and tasks and the necessary organisational preparations to be made for carrying out the studies. A systematic determination of reliability parameters and establishment of suitable computer codes are one of the major tasks in the preparatory phase, and information for further quantification of safety reserves and more plant-specific emergency management plans will be major results of the studies. (orig.) [de

  3. Intermediate size LWR plant study for process heat plus power. Volume 1. Executive summary

    Head, M.A.

    1977-01-01

    The appropriateness of intermediate sized LWRs is evaluated for application to the process industry and for cogeneration of electric power and process steam. This brief study is directed toward determination of whether such plants show enough promise to warrant more detailed investigation. In light of higher fossil fuel costs, the study shows that intermediate sized, standardized power plants potentially are economically competitive for such industrial applications. A representative intermediate sized operating plant of the BWR/4 design class, the Swiss Muhleberg unit (1000 MWt) has been examined with respect to design, licensability, capacity factor and cost. It has operated at high capacity factor (approximately 75 percent) since turnover 11/72. Its cost when escalated from 1969 to 1976 ($620/kWe) appears competitive. Cost adjustments ($100-$250/kWe) included at this stage for compliance with current licensing and mandatory design requirements are only a preliminary estimate. Further study is recommended to confirm necessary regulatory upgrades for this BWR/4 nuclear plant and to explore specific cost economies through replication leading to a program for construction of a demonstration plant

  4. Feasibility study on replacement of power plant and desalination plant in Aktau City, Manghistau Region, Republic of Kazakhstan

    NONE

    2001-03-01

    For the purpose of conserving energy and reducing greenhouse effect gas emission, feasibility study was conducted for improvement of efficiency of power generation/desalination facilities at MAEK Energy Center, Aktau City, Manghistau, Kazakhstan. Presently, the main facilities are the conventional natural gas fired power plant, evaporation type seawater desalination facility, hot water production facility, etc. In the project, introduction of the following was planned to be made: cogeneration facility composed of two units of 1,100-degree C class gas turbine and reverse osmosis (RO) type desalination facility for drinking water production with a capacity of 50,000 t/d. As a result of the study, the energy conservation amount in this project was 151,900-165,400 toe/y in power generation facility, and the greenhouse effect gas reduction amount was 355,000-387,000 t-CO2/y in power generation facility and 268,000 t-CO2/y in desalination facility. The construction cost and operational cost of the plant were 45.7 billion yen and 2.8 billion yen/y. In the economical estimation, ROI and ROE before tax were 7.4 and 34.8, respectively, which were considered to be appropriate values as social infrastructure related conditions. (NEDO)

  5. Fusion power plant simulations: a progress report

    Cook, J.M.; Pattern, J.S.; Amend, W.E.

    1976-01-01

    The objective of the fusion systems analysis at ANL is to develop simulations to compare alternative conceptual designs of magnetically confined fusion power plants. The power plant computer simulation progress is described. Some system studies are also discussed

  6. A basic study for development of environmental standard review plan of Nuclear Power Plant

    Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

    1999-12-15

    In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

  7. A study on methodologies for assessing safety critical network's risk impact on Nuclear Power Plant

    Lim, T. J.; Lee, H. J.; Park, S. K.; Seo, S. J.

    2006-08-01

    The objectives of this project is to investigate and study existing reliability analysis techniques for communication networks in order to develop reliability analysis models for Nuclear Power Plant's safety-critical networks. It is necessary to make a comprehensive survey of current methodologies for communication network reliability. Major outputs of the first year study are design characteristics of safety-critical communication networks, efficient algorithms for quantifying reliability of communication networks, and preliminary models for assessing reliability of safety-critical communication networks

  8. Use of complex electronic equipment within radiative areas of PWR power plants: feability study

    Fremont, P.; Carquet, M.

    1988-01-01

    EDF has undertaken a study in order to evaluate the technical and economical feasibility of using complex electronic equipment within radiative areas of PWR power plants. This study lies on tests of VLSI components (Random Access Memories) under gamma rays irradiations, which aims are to evaluate the radiation dose that they can withstand and to develop a selection method. 125 rad/h and 16 rad/h tests results are given [fr

  9. Geothermal Power Generation Plant

    Boyd, Tonya [Oregon Inst. of Technology, Klamath Falls, OR (United States). Geo-Heat Center

    2013-12-01

    Oregon Institute of Technology (OIT) drilled a deep geothermal well on campus (to 5,300 feet deep) which produced 196°F resource as part of the 2008 OIT Congressionally Directed Project. OIT will construct a geothermal power plant (estimated at 1.75 MWe gross output). The plant would provide 50 to 75 percent of the electricity demand on campus. Technical support for construction and operations will be provided by OIT’s Geo-Heat Center. The power plant will be housed adjacent to the existing heat exchange building on the south east corner of campus near the existing geothermal production wells used for heating campus. Cooling water will be supplied from the nearby cold water wells to a cooling tower or air cooling may be used, depending upon the type of plant selected. Using the flow obtained from the deep well, not only can energy be generated from the power plant, but the “waste” water will also be used to supplement space heating on campus. A pipeline will be construction from the well to the heat exchanger building, and then a discharge line will be construction around the east and north side of campus for anticipated use of the “waste” water by facilities in an adjacent sustainable energy park. An injection well will need to be drilled to handle the flow, as the campus existing injection wells are limited in capacity.

  10. Nuclear power plant analyzer

    Stritar, A.

    1986-01-01

    The development of Nuclear Power Plant Analyzers in USA is described. There are two different types of Analyzers under development in USA, the forst in Idaho and Los Alamos national Lab, the second in brookhaven National lab. That one is described in detail. The computer hardware and the mathematical models of the reactor vessel thermalhydraulics are described. (author)

  11. Nuclear power plant

    Wieser, R.

    1979-01-01

    The reactor pressure vessel consists of two parts. A cylindrical lower part with a hemispherical steel roof is placed at some distance within an equally shaped pressure vessel of concrete. Both vessels are standing on a common bottom plate. The interspace is kept at subpressure. It serves to contain ring galleries, elevator shafts, and power plant components. (GL) [de

  12. Nuclear Power Plant Technician

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  13. Steam power plant

    Campbell, J.W.E.

    1981-01-01

    This invention relates to power plant forced flow boilers operating with water letdown. The letdown water is arranged to deliver heat to partly expanded steam passing through a steam reheater connected between two stages of the prime mover. (U.K.)

  14. Simplified drive system models for power system transient studies in industrial plants

    Chen, Peiyuan; Sannino, Ambra

    2007-01-01

    In order to simulate industrial plants for different power system transient studies, simplified adjustable speed drive (ASD) models are needed. For power system transient studies such as assessing the voltage dip ride-through capability of ASDs, detailed representation of semiconductor valve...... switching can be avoided, thereby making possible to increase the time step of the simulation. In this paper, simplified ASD models are developed and compared with corresponding detailed models. The performance of the simplified models is assessed when increasing the simulation step as much as possible...

  15. Power plants 2009. Lectures

    2009-01-01

    Within the Annual Conference 2009 of the VGB PowerTech e.V. (Essen, Federal Republic of Germany) from 23rd to 25th May, 2009, in Lyon (France) the following lectures were held: (1) Electricity demand, consequences of the financial and economic crisis - Current overview 2020 for the EU-27 (Hans ten Berge); (2) Status and perspectives of the electricity generation mix in France (Bernard Dupraz); (3) European electricity grid - status and perspective (Dominique Maillard); (4) Technologies and acceptance in the European energy market (Gordon MacKerran); (5) EPR construction in Finland, China, France, (Claude Jaouen); (6) EPR Flamanville 3: A project on the path towards nuclear revival (Jacques Alary); (7) Worldwide nuclear Revival and acceptance (Luc Geraets); (8) An overview on the status of final disposal of radioactive wastes worldwide (Piet Zuidema); (9) Who needs pumped storage plants? PSP are partner to grid stability and renewable energies (Hans-Christoph Funke); (10) Sustainable use of water resources to generate electricity safely and efficiently (Patrick Tourasse); (11) The growth strategy of RWE Innogy - Role of RES in RWE strategy (Fritz Vahrenholt); (12) Solar technologies towards grid parity - key factors and timeframe (G. Gigliucci); (13) Overview on CCS technologies and results of Vattenfalls oxyfuel pilot plant (Philippe Paelinck); (14) Development perspectives of lignite-based IGCC-plants with CCS (Dietmar Keller); (15) Post combustion capture plants - concept and plant integration (Wolfgang Schreier); (16) CCS fossil power generation in a carbon constraint world (Daniel Hofmann); (17) CEZ group strategy in Central and South Eastern Europe (Jan Zizka); (18) Strategy and projects of DONG Energy (Jens Erik Pedersen); (19) E.ON coal-based power generation of the future - The highly efficient power plant and downstream separation of carbon dioxide (Gerhard Seibel); (20) Final sage of first supercritical 460 MW e l. CFB Boiler construction - firs

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

    Jiang Zhenbiao; Li Guanying; Liu Zhicheng

    2013-01-01

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

  17. Beloyarsk Nuclear Power Plant

    1997-01-01

    The Beloyarsk Nuclear Power Plant (BNPP) is located in Zarechny, approximately 60 km east of Ekaterinberg along the Trans-Siberian Highway. Zarechny, a small city of approximately 30,000 residents, was built to support BNPP operations. It is a closed city to unescorted visitors. Residents must show identification for entry. BNPP is one of the first and oldest commercial nuclear power plants in Russia and began operations in 1964. As for most nuclear power plants in the Russian Federation, BNPP is operated by Rosenergoatom, which is subordinated to the Ministry of Atomic Energy of the Russian Federation (Minatom). BNPP is the site of three nuclear reactors, Units 1, 2, and 3. Units 1 and 2, which have been shut-down and defueled, were graphite moderated reactors. The units were shut-down in 1981 and 1989. Unit 3, a BN-600 reactor, is a 600 MW(electric) sodium-cooled fast breeder reactor. Unit 3 went on-line in April 1980 and produces electric power which is fed into a distribution grid and thermal power which provides heat to Zarechny. The paper also discusses the SF NIKIET, the Sverdiovsk Branch of NIKIET, Moscow, which is the research and development branch of the parent NIKEIT and is primarily a design institute responsible for reactor design. Central to its operations is a 15 megawatt IVV research reactor. The paper discusses general security and fissile material control and accountability at these two facilities

  18. Results from study of potential early commercial MHD power plants and from recent ETF design work. [Engineering Test Facility

    Hals, F.; Kessler, R.; Swallom, D.; Westra, L.; Zar, J.; Morgan, W.; Bozzuto, C.

    1980-01-01

    The study deals with different 'moderate technology' entry-level commercial MHD power plants. Two of the reference plants are based on combustion of coal with air preheated in a high-temperature regenerative air heater separately fired with a low-BTU gas produced in a gasifier integrated with the power plant. The third reference plant design is based on the use of oxygen enriched combustion air. Performance calculations show that an overall power plant efficiency of the order of 44% can be reached with the use of oxygen enrichment.

  19. Organizing nuclear power plant operation

    Adams, H.W.; Rekittke, K.

    1987-01-01

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

  20. Nuclear power plant safety

    Otway, H.J.

    1974-01-01

    Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

  1. Study of seismic design bases and site conditions for nuclear power plants

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches

  2. Study of seismic design bases and site conditions for nuclear power plants

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

  3. Economic modeling and parametric studies for SOMBRERO - a laser-driven IFE power plant

    Meier, W.R.; Rosenberg, C.W. Jr. von

    1992-01-01

    Economic modeling and parametric studies for the SOMBRERO laser-driven inertial fusion energy (IFE) electric power plant have been conducted to determine the most attractive operating point. Cost scaling relationships have been developed and integrated into a cost-performance model of the plant. The figure-of-merit for determining the most attractive design point is the constant-dollar cost of electricity. Results are presented as a function of the driver energy. The sensitivity of the results to variations in the assumed net electric output and target performance is also examined

  4. Economic modeling and parametric studies for OSIRIS - a HIB-driven IFE power plant

    Meier, W.R.; Bieri, R.L.

    1992-01-01

    Economic modeling and parametric studies for the Osiris HIB-driven inertial fusion energy (IFE) electric power plant have been conducted to determine the most attractive operating point. Cost scaling relationships have been developed and integrated into a cost-performance model of the plant. The figure-of-merit for determining the most attractive design point is the constant-dollar cost of electricity. Results are presented as a function of the driver energy. The sensitivity of the results to variations in the assumed net electric output and target performance is also examined

  5. Case studies on the feasibility of the transient analysis system STAR in German nuclear power plants

    Buettner, W.E.; Felkel, L.; Zapp, A.

    1984-01-01

    On the basis of distubances which actually have occurred in German nuclear power plants a case-study has been performed to evaluate the feasibility of the computer-based disturbance analysis system STAR. By means of a compact plant simulator the disturbances collected have been remodelled and anlysed, on-line, with the disturbance analysis system STAR. In the last phase of the project experiments have been performed with reactor operators to get their reaction to, and opinion on, computerbased-operator aids. (orig.) [de

  6. Studies of potential severe accidents in Finnish nuclear power plants. Quarterly report 3. quarter 1987

    Aro, Ilari.

    1989-07-01

    This thesis is based on six publications dealing with severe accident studies in Finnish nuclear power plants. Main emphasis has been put on general technical bases and methodologies applied in severe accident evaluation in Finland. As an example of the use of the analysis and evaluation methods, the analysis of one representative accident sequence, t otal loss of AC power , has been presented for both Finnish power plant types. This accident sequence is required to be analyzed in the Finnish safety guide YVL 2.2 which deals with transient and accident analyses as a basis of technical solutions at nuclear powr plants. Two different analysis methods, MAAP 3.0 and MARCH 3/STCP have been used for receiving as complete a picture as possible of the flow of events and for verifying the models to some extent. Besides the use of the two different models, the method of sensitivity analysis has been used for evaluating the effects of some important technical parameters on the accident flow. Finally, conclusions of the applicability of the two methods for analyzing severe accident sequences in Finnish plants have been discussed

  7. Workplace monitoring and occupational health studies in the Sostanj Thermal Power Plant, Slovenia

    Jacimovic, R.; Falnoga, I.; Jeran, Z.; Byrne, A.R.; Kobal, A.B.; Stropnik, B.

    1998-01-01

    Up to now, only a few investigations have been performed in the Sostanj Thermal Power Plant (TPP) involving comprehensive studies of trace elements, toxic elements, heavy metals and radionuclides in the workplaces. The aim of the project is development and application of nuclear and nuclear-related analytical techniques for workplace pollution and occupational health studies, leading to formation of a database concerning the trace element air pollution inside the Sostanj Thermal Power Plant. In this report, the emphasis is on the methodology and analytical development (neutron activation analysis, X-ray spectrometry, total-reflection X-ray fluorescence (TXRF) spectroscopy and proton induced X-ray emission (PIXE)), and to a lesser extent on the results obtained up to now. Analytical results for several certified reference materials of similar matrix as the real samples investigated were obtained. Results obtained by the k 0 -standardization method and XRF technique for aerosols (coarse and fine fractions) ore also presented and discussed. (author)

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

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

    1986-07-01

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

  9. Development of a New Safety Culture Assessment Method for Nuclear Power Plants (NPPs) (A study to suggest a new safety culture assessment method in nuclear power plants)

    Han, Sang Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2014-08-15

    This study is conducted to suggest a new safety culture assessment method in nuclear power plants. Criteria with various existing safety culture analysis methods are united, and reliability analysis methods are applied. The concept of the most representative methods, Fault Tree Analysis (FTA) and Failure Mode and Effect Analysis (FMEA), are adopted to assess safety culture. Through this application, it is expected that the suggested method will bring results with convenience and objectiveness.

  10. Development of a New Safety Culture Assessment Method for Nuclear Power Plants (NPPs) (A study to suggest a new safety culture assessment method in nuclear power plants)

    Han, Sang Min; Seong, Poong Hyun

    2014-01-01

    This study is conducted to suggest a new safety culture assessment method in nuclear power plants. Criteria with various existing safety culture analysis methods are united, and reliability analysis methods are applied. The concept of the most representative methods, Fault Tree Analysis (FTA) and Failure Mode and Effect Analysis (FMEA), are adopted to assess safety culture. Through this application, it is expected that the suggested method will bring results with convenience and objectiveness

  11. Friction and wear studies of nuclear power plant components in pressurized high temperature water environments

    Ko, P.L.; Zbinden, M.; Taponat, M.C.; Robertson, M.F.

    1997-01-01

    The present paper is part of a series of papers aiming to present the friction and wear results of a collaborative study on nuclear power plant components tested in pressurized high temperature water. The high temperature test facilities and the methodology in presenting the kinetics and wear results are described in detail. The results of the same material combinations obtained from two very different high temperature test facilities (NRCC and EDF) are presented and discussed. (K.A.)

  12. A sensitivity study of seismic structure-soil-structure interaction problems for nuclear power plants

    Matthees, W.; Magiera, G.

    1982-01-01

    A sensitivity study for the interaction effects of adjacent structures of nuclear power plants caused by horizontal seismic excitation has been performed. The key structural and soil parameters for linear and for nonlinear behaviour were varied within their applicable bandwidth. It has been shown that the interaction phenomena can contribute to the response of structures to such a large extent that it cannot be disregarded. (orig.)

  13. Study on safety subsidiary objective of nuclear power plant in USA

    Chen Yan; Zhang Chunming; Fu Zhiwei; Song Wei; Li Chaojun; Wang Zhe; Zuo Jiaxu

    2013-01-01

    This paper reviewed the development of the quantitative safety objective and subsidiary objective in USA. The expressions of CDF and LERF were obtained according to NUREG-1150. The relationship between the subsidiary objective and the quantitative safety objective was derived. The method was compared with that used in NUREG-1860. The requirements of safety objective for the future nuclear power plant and the development of probabilistic safety analysis (PSA) technology in USA were studied and can be used as reference in China. (authors)

  14. Preliminary Study on Impact Resistances of Fiber Reinforced Concrete Applied Nuclear Power Plants

    Jin, Byeong Moo; Kim, Young Jin; Jeon, Se Jin

    2013-01-01

    Studies to improve the impact resistance depending upon design parameters for fiber reinforced concrete, such as type of fibers and application ratio, are in progress. Authors assessed first the impact resistance of concrete walls depending upon fiber types and missile impact velocities. The safety assessment of nuclear power plants against large civil aircraft crashes have been accomplished for normal concrete and fiber reinforced concretes in this study. Studies on the safety assessments on the nuclear power plants against large civil aircraft crashes are ongoing actively. As a step of evaluating the applicability of fiber reinforced concrete in means of ensuring more structural safety of the nuclear power plants against impact, the impact resistance for the 1% steel and 2% polyamide fiber reinforced concretes have been evaluated. For reactor containment building structures, it seem there is no impact resistance enhancement of fiber reinforced concrete applied to reactor containment building in the cases of impact velocity 150 m/sec considered in this study. However this results from the pre-stressing forces which introduce compressive stresses in concrete wall and dome section of reactor containment building. Nonetheless there may be benefits to apply fiber reinforced concrete to nuclear power plants. For double containment type reactor containment building, the outer structure is a reinforced concrete structure. The impact resistances for non pre-stressed cylindrical reactor containment buildings are enhanced by 23 to 47 % for 2 % polyamide fiber reinforced concretes and 1 % steel fiber reinforced concretes respectively. For other buildings such as auxiliary building, compound building and fuel storage building surrounding the reactor containment building, there are so many reinforced concrete walls which are anticipated some enhancements of impact resistance by using fiber reinforced concretes. And heavier or faster large civil aircraft impacts produce higher

  15. Preliminary Study on Impact Resistances of Fiber Reinforced Concrete Applied Nuclear Power Plants

    Jin, Byeong Moo; Kim, Young Jin; Jeon, Se Jin [Daewoo E and C Co. Ltd., Suwon (Korea, Republic of)

    2013-10-15

    Studies to improve the impact resistance depending upon design parameters for fiber reinforced concrete, such as type of fibers and application ratio, are in progress. Authors assessed first the impact resistance of concrete walls depending upon fiber types and missile impact velocities. The safety assessment of nuclear power plants against large civil aircraft crashes have been accomplished for normal concrete and fiber reinforced concretes in this study. Studies on the safety assessments on the nuclear power plants against large civil aircraft crashes are ongoing actively. As a step of evaluating the applicability of fiber reinforced concrete in means of ensuring more structural safety of the nuclear power plants against impact, the impact resistance for the 1% steel and 2% polyamide fiber reinforced concretes have been evaluated. For reactor containment building structures, it seem there is no impact resistance enhancement of fiber reinforced concrete applied to reactor containment building in the cases of impact velocity 150 m/sec considered in this study. However this results from the pre-stressing forces which introduce compressive stresses in concrete wall and dome section of reactor containment building. Nonetheless there may be benefits to apply fiber reinforced concrete to nuclear power plants. For double containment type reactor containment building, the outer structure is a reinforced concrete structure. The impact resistances for non pre-stressed cylindrical reactor containment buildings are enhanced by 23 to 47 % for 2 % polyamide fiber reinforced concretes and 1 % steel fiber reinforced concretes respectively. For other buildings such as auxiliary building, compound building and fuel storage building surrounding the reactor containment building, there are so many reinforced concrete walls which are anticipated some enhancements of impact resistance by using fiber reinforced concretes. And heavier or faster large civil aircraft impacts produce higher

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

    1997-01-01

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

  17. Latina nuclear power plant

    1976-03-01

    In the period under review, the Latina power plant produced 1009,07 million kWh with a utilization factor of 72% and an availability factor of 80,51%. The disparity between the utilization and availability factors was mainly due to the shutdown of the plant owing to trade union strife. The reasons for non-availability (19,49%) were almost all related to the functioning of the conventional part and the general servicing of the plant (18 September-28 October). During the shutdown for maintenance, an inspection of the steel members and parts of the core stabilizing structure was made in order to check for the familiar oxidation phenomena caused by CO 2 ; the results of the inspection were all satisfactory. Operation of the plant during 1974 was marked by numerous power cutbacks as a result of outages of the steam-raising units (leaks from the manifolds) and main turbines (inspection and repairs to the LP rotors). Since it was first brought into commercial operation, the plant has produced 13,4 thousand million kWh

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

    Kim, S. H.; Park, J.

    2008-01-01

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

  19. Wind power plant

    Weiss, G

    1975-11-20

    A wind power plant is proposed suitable for electicity generation or water pumping. This plant is to be self-adjusting to various wind velocities and to be kept in operation even during violent storms. For this purpose the mast, carrying the wind rotor and pivotable around a horizontal axis is tiltable and equipped with a wind blind. Further claims contain various configurations of the tilting base resp. the cut in of an elastic link, the attachment and design of the wind blind as well as the constructive arrangement of one or more dynamos.

  20. Power plant process computer

    Koch, R.

    1982-01-01

    The concept of instrumentation and control in nuclear power plants incorporates the use of process computers for tasks which are on-line in respect to real-time requirements but not closed-loop in respect to closed-loop control. The general scope of tasks is: - alarm annunciation on CRT's - data logging - data recording for post trip reviews and plant behaviour analysis - nuclear data computation - graphic displays. Process computers are used additionally for dedicated tasks such as the aeroball measuring system, the turbine stress evaluator. Further applications are personal dose supervision and access monitoring. (orig.)

  1. Fossil power plant automation

    Divakaruni, S.M.; Touchton, G.

    1991-01-01

    This paper elaborates on issues facing the utilities industry and seeks to address how new computer-based control and automation technologies resulting from recent microprocessor evolution, can improve fossil plant operations and maintenance. This in turn can assist utilities to emerge stronger from the challenges ahead. Many presentations at the first ISA/EPRI co-sponsored conference are targeted towards improving the use of computer and control systems in the fossil and nuclear power plants and we believe this to be the right forum to share our ideas

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

    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

  3. Design study on the efficiency of the thermal scheme of power unit of thermal power plants in hot climates

    Sedlov, A.; Dorokhov, Y.; Rybakov, B.; Nenashev, A.

    2017-11-01

    At the stage of pre-proposals unit of the thermal power plants for regions with a hot climate requires a design study on the efficiency of possible options for the structure of the thermal circuit and a set of key parameters. In this paper, the thermal circuit of the condensing unit powerfully 350 MW. The main feature of the external conditions of thermal power plants in hot climates is the elevated temperature of cooling water of the turbine condensers. For example, in the Persian Gulf region as the cooling water is sea water. In the hot season of the year weighted average sea water temperature of 30.9 °C and during the cold season to 22.8 °C. From the turbine part of the steam is supplied to the distillation-desalination plant. In the hot season of the year heat scheme with pressure fresh pair of 23.54 MPa, temperature 570/560 °C and feed pump with electric drive (EDP) is characterized by a efficiency net of 0.25% higher than thermal schem with feed turbine pump (TDP). However, the supplied power unit with PED is less by 11.6 MW. Calculations of thermal schemes in all seasons of the year allowed us to determine the difference in the profit margin of units of the TDP and EDP. During the year the unit with the TDP provides the ability to obtain the profit margin by 1.55 million dollars more than the unit EDP. When using on the market subsidized price of electricity (Iran) marginal profit of a unit with TDP more at 7.25 million dollars.

  4. Gas power plant with CO2 handling. A study of alternative technologies

    Bolland, Olav; Hagen, Roger I.; Maurstad, Ola; Tangen, Grethe; Juliussen, Olav; Svendsen, Hallvard

    2002-01-01

    The report documents a study which compares 12 different technologies for gas power plants with CO 2 handling. The additional costs in removing the CO 2 in connection with electricity production is calculated to at least 18-19 oere /kWh compared to conventional gas power production without CO 2 capture. The calculated extra costs are somewhat higher than previously published figures. The difference is mainly due to that the estimated costs for pipelines and injection system for CO 2 are higher than in other studies. The removal of CO 2 in connection with gas power production implies increased use of natural gas. The most developed technologies would lead to a procentual increase in the gas consumption per kWh electricity of 18-25%. Gas power plants based on the present technologies would have efficiencies in the size of 46-49%. The efficiency of power plants without CO 2 handling is supposed to be 58%. There is no foundation for pointing out a ''winner's' among the compared technologies in the study. The present available technologies excepted, there are no technology which stands out as better than the others from an economic viewpoint. Gas turbine with membrane based separation of oxygen from air (AZEP) has a potential for lower costs but implies challenging technological development and thence considerable technological risks. Two technologies, capture of carbon from natural gas previous to combustion and exhaust gas purification based on absorption, may be employed in 3 - 4 years. The other technologies require more development and maturing. Three of the technologies may be particularly interesting because hydrogen may be produced as a byproduct. Demonstration plant and choice of technology: 1) There is a limited need for demonstration plants with respect to technology development. 2) It is important for the technology development to be able to test various technologies in a laboratory or in a flexible pilot plant. 3) Many technologies and components may be

  5. A study on the water-proof of structures in electric power plants

    Kown, Ki Ju [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    As some of the currently used waterproofing systems are found to be un properly applied for each building type or environmental condition, adequate methods or systems are required to determine the proper materials effectiveness of waterproofing. Performance tests were conducted in order to examine the applicability and effectiveness of previously studied waterproofing systems and to propose the improvement directions of the waterproofing systems. Waterproofing systems and methods were systematized in order to be applied adequately considering the structure parts, structural and environmental conditions. -Analysis of waterproof methods and materials -Characteristics related with waterproofing of power plants structures -Site investigation of waterproofing of power plant structures -Determination of optimal waterproofing material, system and construction method -Waterproofing performance tests (author). 96 refs., 223 figs.

  6. Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

    Bertsche, K.; Hoermann, E.

    1991-01-01

    The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

  7. Environmental studies in conjunction with the construction of nuclear power plants Pt. 2

    Horvath, L.G.; Bede, G.; Gacs, I.

    1980-01-01

    A status-of-the-art report is presented to summarize the studies in progress in Hungary concerning the radionuclide release of nuclear power plants and the motion and migration of radionuclides in the atmosphere. The presently available computerized models are described, their objectives, performances and advantages are discussed. Some examples are given to illustrate the applicability of the various models. They will be adapted to the local environmental, meteorological and architectural conditions of the Paks nuclear power plant under construction. The cooperation of research groups participating in the development or adaption of the different computerized models will continue during the start-up and operation of the Paks-1 reactor and the models will be improved on the basis of field experiences. New models will also be developed. (D.Gy.)

  8. A study on the water-proof of structures in electric power plants

    Kown, Ki Ju [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    As some of the currently used waterproofing systems are found to be un properly applied for each building type or environmental condition, adequate methods or systems are required to determine the proper materials effectiveness of waterproofing. Performance tests were conducted in order to examine the applicability and effectiveness of previously studied waterproofing systems and to propose the improvement directions of the waterproofing systems. Waterproofing systems and methods were systematized in order to be applied adequately considering the structure parts, structural and environmental conditions. -Analysis of waterproof methods and materials -Characteristics related with waterproofing of power plants structures -Site investigation of waterproofing of power plant structures -Determination of optimal waterproofing material, system and construction method -Waterproofing performance tests (author). 96 refs., 223 figs.

  9. Birth Outcomes after the Fukushima Daiichi Nuclear Power Plant Disaster: A Long-Term Retrospective Study.

    Leppold, Claire; Nomura, Shuhei; Sawano, Toyoaki; Ozaki, Akihiko; Tsubokura, Masaharu; Hill, Sarah; Kanazawa, Yukio; Anbe, Hiroshi

    2017-05-19

    Changes in population birth outcomes, including increases in low birthweight or preterm births, have been documented after natural and manmade disasters. However, information is limited following the 2011 Fukushima Daiichi Nuclear Power Plant Disaster. In this study, we assessed whether there were long-term changes in birth outcomes post-disaster, compared to pre-disaster data, and whether residential area and food purchasing patterns, as proxy measurements of evacuation and radiation-related anxiety, were associated with post-disaster birth outcomes. Maternal and perinatal data were retrospectively collected for all live singleton births at a public hospital, located 23 km from the power plant, from 2008 to 2015. Proportions of low birthweight (effects on maternal and perinatal health.

  10. Energy and environmental studies associated to the emergency plan of natural gas thermal power plants

    Ferreira, Vinicius V.M.; Grynberg, Sueli E.; Aronne, Ivan D.; Jacomino, Vanusa M.F.; Branco, Otavio E.A.; Martinez, Carlos B.; Versiani, Bruno R.

    2002-01-01

    This work presents a first exertion to evaluate the environmental impacts due to the operation of planned gas power plants. This study was carried out with the model EcoSense, that is a computer program developed for the quantification of environmental impacts and their external costs resulting from the operation of thermal power plants or other industrial activities. EcoSense is still in development and the achieved results should still be considered with caution although it becomes clear the potentiality of the use of this tool in the support of the decision making process in energy planning. Based on the method of approach of the damage function established in the ExternE project this program provides models for an integrated evaluation of the impact rate from the air pollutants resulting from burning fossil fuel, which are transported by the air. (author)

  11. CO2 capture from power plants: Part I. A parametric study of the technical performance based on monoethanolamine

    Abu-Zahra, Mohammad R.M.; Schneiders, Léon H.J.; Niederer, John; Feron, Paul H.M.; Versteeg, Geert

    2007-01-01

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  12. CO2 capture from power plants. Part I : A parametric study of the technical performance based on monoethanolamine

    Abu-Zahra, M. R. M.; Schneiders, L. H. J.; Niederer, J. P. M.; Feron, P. H. M.; Versteeg, G. F.

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  13. Virtual power plant auctions

    Ausubel, Lawrence M.; Cramton, Peter

    2010-01-01

    Since their advent in 2001, virtual power plant (VPP) auctions have been implemented widely. In this paper, we describe the simultaneous ascending-clock auction format that has been used for virtually all VPP auctions to date, elaborating on other design choices that most VPP auctions have had in common as well as discussing a few aspects that have varied significantly among VPP auctions. We then evaluate the various objectives of regulators in requiring VPP auctions, concluding that the auctions have been effective devices for facilitating new entry into electricity markets and for developing wholesale power markets. (author)

  14. Virtual power plant auctions

    Ausubel, Lawrence M.; Cramton, Peter [Department of Economics, University of Maryland, College Park, MD 20742 (United States)

    2010-12-15

    Since their advent in 2001, virtual power plant (VPP) auctions have been implemented widely. In this paper, we describe the simultaneous ascending-clock auction format that has been used for virtually all VPP auctions to date, elaborating on other design choices that most VPP auctions have had in common as well as discussing a few aspects that have varied significantly among VPP auctions. We then evaluate the various objectives of regulators in requiring VPP auctions, concluding that the auctions have been effective devices for facilitating new entry into electricity markets and for developing wholesale power markets. (author)

  15. Study on effective methods to call attention in power plant sites. Towards sharing know-how

    Tsukada, Tetsuya; Nakamura, Hajime

    1999-01-01

    Methods to call attention during field work in nuclear power plants have not obtained the desired results due to redundancy and poor theoretical support. From the points of view of psychology and human engineering, we theoretically examined the validity of each of the following methods for calling attention: methods deployed in power plants, methods obtained through case studies in other industries, and newly developed methods, and then systematized these methods. Using five typical operations with different operating characteristics as models, we also determined methods deployed for each situation in the operation process. Then we determined and categorized the ways of utilizing methods to call attention according to each operating characteristic. With the aim of utilizing these results in many power plants and promoting the sharing of know-how concerning calling attention, we put together an easy-to-understand 'instruction manual', which contains know-how concerning methods to call attention and an introduction to the newly developed methods. Moreover, we established a 'database' (with a registration function) of methods to call attention, which contains organized methods and patterns of utilizing such methods in each operating characteristic. The present study is thus a report that aims at sharing the know-how, centered on this database. (author)

  16. Numerical Hydraulic Study on Seawater Cooling System of Combined Cycle Power Plant

    Kim, J. Y.; Park, S. M.; Kim, J. H.; Kim, S. W.

    2010-06-01

    As the rated flow and pressure increase in pumping facilities, a proper design against surges and severe cavitations in the pipeline system is required. Pressure surge due to start-up, shut-down process and operation failure causes the water hammer in upstream of the closing valve and the cavitational hammer in downstream of the valve. Typical cause of water hammer is the urgent closure of valves by breakdown of power supply and unexpected failure of pumps. The abrupt changes in the flow rate of the liquid results in high pressure surges in upstream of the valves, thus kinetic energy is transformed into potential energy which leads to the sudden increase of the pressure that is called as water hammer. Also, by the inertia, the liquid continues to flow downstream of the valve with initial speed. Accordingly, the pressure decreases and an expanding vapor bubble known as column separation are formed near the valve. In this research, the hydraulic study on the closed cooling water heat exchanger line, which is the one part of the power plant, is introduced. The whole power plant consists of 1,200 MW combined power plant and 220,000 m3/day desalination facility. Cooling water for the plant is supplied by sea water circulating system with a capacity of 29 m3/s. The primary focus is to verify the steady state hydraulic capacity of the system. The secondary is to quantify transient issues and solutions in the system. The circuit was modeled using a commercial software. The stable piping network was designed through the hydraulic studies using the simulation for the various scenarios.

  17. Nuclear power plant

    Aisaka, Tatsuyoshi; Kamahara, Hisato; Yanagisawa, Ko.

    1982-01-01

    Purpose: To prevent corrosion stress cracks in structural materials in a BWR type nuclear power plant by decreasing the oxygen concentration in the reactor coolants. Constitution: A hydrogen injector is connected between the condensator and a condensate clean up system of a nuclear power plant. The injector is incorporated with hydrogenated compounds formed from metal hydrides, for example, of alloys such as lanthanum-nickel alloy, iron titanium alloy, vanadium, palladium, magnesium-copper alloy, magnesium-nickel alloy and the like. Even if the pressure of hydrogen obtained from a hydrogen bomb or by way of water electrolysis is changed, the hydrogen can always be injected into a reactor coolant at a pressure equal to the equilibrium dissociation pressure for metal hydride by introducing the hydrogen into the hydrogen injector. (Seki, T.)

  18. Rock cavity construction of a nuclear power plant: a case study

    Loken, P.C.; Bakke, J.; Gloersen, I.

    1979-01-01

    The major findings of a comprehensive study of the major aspects of rock cavity construction of a large nuclear power plant are: (1) current technology is adequate for the realization of such construction; (2) a method for estimating the probability of rock fallout and gross cavity instability is presently not available; (3) certain design modifications and amplifications must be made to prevent dependent failures; (4) no significant reduction in the immediate radiological effects of Class 9 accidents will result unless special design measures are made for this purpose; (5) the vulnerability of the plant to certain external effects is significantly reduced; (6) the total time for the realization of such construction will be significantly longer than that for a traditionally constructed plant; and (7) the extra cost will be substantial

  19. Impact of coal-fired thermal power plant emissions on surrounding vegetative environment: a case study

    Soni, D.K.; Senger, C.B.S.

    1993-01-01

    Vegetative system around the thermal power plants are exposed to perpetual emissions of particulates as well as gaseous pollutants in various forms and nature. These emissions evidently are reflected in plant responses. In order to assess the response of natural flora of this region, 2 plant species, that is Mangifera indica and Holarrhina artidysentrica and certain pollution sensitive parameter, such as leaf area, pH of wash water of foliage and sugar content of the leaves were identified for this study. It was observed that the pH of wash solution of leaves was close to neutral in upstream locations and in polluted zone pH was acidic. Leaf area was higher in least polluted zone and lower in more polluted locations. Dust deposition on leaves was observed be lower in upstream locations and higher in influenced areas. Sugar variations in leaves showed negative impact in affected areas. (author). 9 refs., 5 tabs

  20. Application of ICP-MS to a trace elements mass balance study in a power plant

    Bettinelli, M.; Spezia, S.; Fiore, A.; Pastorelli, N.; Terni, C.; Holland, G.; Tanner, S.D.

    2001-01-01

    The distributions of seven trace elements in a power plant are detd. in 3 fuels (Orimulsion, coal, and fuel oil) and output flows, i.e., ash, wastewater, gypsum, and emulsions by using ICP-MS. The power plant is equipped with sulfur oxide and nitrogen oxide removal facilities. [on SciFinder (R)

  1. A Post Licensing Study of Community Effects at Two Operating Nuclear Power Plants. Final Report.

    Purdy, Bruce J.; And Others

    In an effort to identify and assess the social, economic, and political effects of nuclear power plant construction and operation upon two host communities (Plymouth, Massachusetts and Waterford, Connecticut), a post-licensing review revealed that the primary impact of the nuclear power plants in both communities was an increase in the property…

  2. Nuclear power plant

    Schabert, H.P.; Laurer, E.

    1976-01-01

    The invention concerns a quick-acting valve on the main-steam pipe of a nuclear power plant. The engineering design of the valve is to be improved. To the main valve disc, a piston-operated auxiliary valve disc is to be assigned closing a section of the area of the main valve disc. This way it is avoided that the drive of the main valve disc has to carry out different movements. 15 sub-claims. (UWI) [de

  3. Fusion power plant economics

    Miller, R.L.

    1996-01-01

    The rationale, methodology, and updated comparative results of cost projections for magnetic-fusion-energy central-station electric power plants are considered. Changing market and regulatory conditions, particularly in the U.S., prompt fundamental reconsideration of what constitutes a competitive future energy-source technology and has implications for the direction and emphasis of appropriate near-term research and development programs, for fusion and other advanced generation systems. 36 refs., 2 figs., 2 tabs

  4. Power plant emissions reduction

    Anand, Ashok Kumar; Nagarjuna Reddy, Thirumala Reddy

    2015-10-20

    A system for improved emissions performance of a power plant generally includes an exhaust gas recirculation system having an exhaust gas compressor disposed downstream from the combustor, a condensation collection system at least partially disposed upstream from the exhaust gas compressor, and a mixing chamber in fluid communication with the exhaust gas compressor and the condensation collection system, where the mixing chamber is in fluid communication with the combustor.

  5. Estimating population exposure to power plant emissions using CALPUFF: a case study in Beijing, China

    Zhou, Y.; Levy, J.I.; Hammitt, J.K.; Evans, J.S. [Harvard University, Boston, MA (USA). School of Public Health, Landmark Center

    2003-02-01

    Power plants are significant emitters of precursor gases of fine particulate matter. To evaluate the public health risk posed by power plants, it is necessary to evaluate population exposure to different pollutants. The concept of intake fraction (the fraction of a pollutant emitted that is eventually inhaled or ingested by a population) has been proposed to provide a simple summary measure of the relationship between emissions and exposure. Currently available intake fraction estimates from developing countries used models that look only at the near field impacts, which may not capture the full impact of a pollution source. This case study demonstrated how the intake fraction of power plant emissions in China can be calculated using a detailed long-range atmospheric dispersion model, CALPUFF. It was found that the intake fraction of primary fine particles is roughly on the order of 10{sup -5}, while the intake fractions of sulfur dioxide, sulfate and nitrate are on the order of 10{sup -6}. These estimates are an order of magnitude higher than the US estimates. The authors also tested how sensitive the results were to key assumptions within the model. The size distribution of primary particles has a large impact on the intake fraction for primary particles while the background ammonia concentration is an important factor influencing the intake fraction of nitrate. The background ozone concentration has a moderate impact on the intake fraction of sulfate and nitrate.

  6. Atomic power plant

    Kawakami, Hiroto.

    1975-01-01

    Object: To permit decay heat to be reliably removed after reactor shut-down at such instance as occurrence of loss of power by means of an emergency water supply pump. Structure: An atomic power plant having a closed cycle constructed by connecting a vapor generator, a vapor valve, a turbine having a generator, a condenser, and a water supply pump in the mentioned order, and provided with an emergency water supply pump operated when there is a loss of power to the water supply pump, a degasifier pressure holding means for holding the pressure of the degasifier by introducing part of the vapor produced from said vapor generator, and a valve for discharge to atmosphere provided on the downstream side of said vapor generator. (Kamimura, M.)

  7. Analytic advanced development in the German Risk Study on Nuclear Power Plants

    1984-01-01

    The study carried out by the Ecological Institute (Oeko-Institut) deals with the difficulties encountered with the decision-making models and statistical models and methods of the German Risk Study on Nuclear Power Plants for the determination of care meltdown frequency and for the estimation of the behaviour of components in the event of a failure. Related deficiencies of the German Risk Study and the absence of completeness and lading representiveness of the course and causes of incidents considered are pointed out. The accident consequences model and the climatological-meteorological data base are considered non-representative. (RF) [de

  8. Thermal and optical study of parabolic trough collectors of Shiraz solar power plant

    Mokhtari, A.; Yaghoubi, M.; Vadiee, A.; Hessami, R. [Shiraz Univ, Shiraz (Iran, Islamic Republic of); Kanan, P. [Renewable Energy Organization of Iran, Tehran (Iran, Islamic Republic of)

    2007-07-01

    The construction of the first 250 KW solar power plant in Shiraz, Iran was discussed. The power plant is comprised of a steam and oil cycle which includes 48 parabolic trough collectors (PTCs). Solar thermal power plants based on PTCs are currently the most successful solar technologies for electricity generation. These power plants are basically composed of a solar collector field and a power block. The solar collector field is designed to collect heat from the sun which it is continuously tracking. The reflecting surface concentrates direct solar radiation in the optical focal line of the collector where the heat collecting element (HCE) is located. The HCE absorbs the reflected energy and transmits it to the heat transfer fluid which is pumped to the conventional power block where electricity is generated. There is potential to significantly increase the performance and reduce the cost of PTC solar thermal electric technologies. However, it is necessary to characterize the optical performance and determine the optical losses of PTCs in order to improve the optical efficiency of these systems and to ensure the desired power quality. In this study, thermocouple sensors were used to record the collector oil inlet and outlet temperature along with the ambient temperature in the PTCs. In addition to measuring the wind speed, the solar beam radiation intensity was measured along with the oil's mass flow rate. All parameters were measured as a function of time. Based on these measurements, the intercept factor value and collector's incidence angle was determined and compared with other large size constructed commercial parabolic collectors. The maximum beam radiation during the experimental period was 735 2mW. The useful heat gain and the collector's instantaneous efficiency as a whole was evaluated on an hourly basis. All these parameters were strongly influenced by the incident beam radiation and found to follow each other. The optical and thermal

  9. Studies of Effect Analysis of Electromagnetic Pulses (EMP) in Operating Nuclear Power Plants (NPP)

    Ye, Song Hae; Ryu, Ho Sun; Kim, Min Yi; Lee, Eui Jong [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    The effect analysis of electromagnetic pulses (EMPs) has been studied for the past year by the Central Research Institute of Korea Hydro Nuclear Power Co. (KHNP) in order to better establish safety measures in operating nuclear power plants. What is an electromagnetic pulse (EMP)? As a general term for high-power electromagnetic radiation, it refers to strong electromagnetic pulses that destroy only electronic equipment devices in a short period without loss of life. The effect analysis of EMPs in operating NPPs and their corresponding safety measures in terms of selecting target devices against EMP impact have been examined in this paper. In general, domestic nuclear power plants do apply the design of fail-safe concepts. For example, if key instruments of a system fail because of EMPs, the control rods of a nuclear reactor are dropped automatically in order to maintain safe conditions of the NPP. Reactor cooling presents no problem because the diesel generator will adopt the analog starting circuit least affected by the electromagnetic waves.

  10. The ARIES-ST study: Assessment of the spherical tokamak concept as fusion power plants

    Najmabadi, F.; Tillack, M.; Miller, R.; Mau, T.K.; Jardin, S.; Stambaugh, R.; Steiner, D.; Waganer, L.

    2001-01-01

    Recent experimental achievements and theoretical studies have generated substantial interest in the spherical tokamak concept. The ARIES-ST study was undertaken as a national U.S. effort to investigate the potential of the spherical tokamak concept as a fusion power plant and as a vehicle for fusion development. The 1000-MWe ARIES-ST power plant has an aspect ratio of 1.6, a major radius of 3.2 m, a plasma elongation (at 95% flux surface) of 3.4 and triangularity of 0.64. This configuration attains a β of 54% (which is 90% of the maximum theoretical β). While the plasma current is 31 MA, the almost perfect alignment of bootstrap and equilibrium current density profiles results in a current-drive power of only 31 MW. The on-axis toroidal field is 2.1 T and the peak field at the TF coil is 7.6 T, which leads to 288 MW of Joule losses in the normal-conducting TF system. The ARIES-ST study has highlighted many areas where tradeoffs among physics and engineering systems are critical in determining the optimum regime of operation for spherical tokamaks. Many critical issues also have been identified which must be resolved in R and D programs. (author)

  11. VGB congress 'Power Plants 2009'

    Anon.

    2009-01-01

    The VGB Congress 'Power Plants 2009' took place in Lyon/France from 23rd to 25th September 2009 and was themed 'Addressing Climate Change - Winning Public Acceptance through Advanced Technologies'. Nearly 1,300 participants attended the plenary and technical lectures and had the opportunity to discus the current topics of electricity and heat generation. The study carried out by VGB according to which EU-27 requires about 475.000 MW of new power plant capacity was also presented. Specific papers were addressing further topics. The Congress was rounded off by a side-programme and technical visits. (orig.)

  12. Compressed Air Quality, A Case Study In Paiton Coal Fired Power Plant Unit 1 And 2

    Indah, Nur; Kusuma, Yuriadi; Mardani

    2018-03-01

    The compressed air system becomes part of a very important utility system in a Plant, including the Steam Power Plant. In PLN’S coal fired power plant, Paiton units 1 and 2, there are four Centrifugal air compressor types, which produce compressed air as much as 5.652 cfm and with electric power capacity of 1200 kW. Electricity consumption to operate centrifugal compressor is 7.104.117 kWh per year. Compressed air generation is not only sufficient in quantity (flow rate) but also meets the required air quality standards. compressed air at Steam Power Plant is used for; service air, Instrument air, and for fly Ash. This study aims to measure some important parameters related to air quality, followed by potential disturbance analysis, equipment breakdown or reduction of energy consumption from existing compressed air conditions. These measurements include counting the number of dust particles, moisture content, relative humidity, and also compressed air pressure. From the measurements, the compressed air pressure generated by the compressor is about 8.4 barg and decreased to 7.7 barg at the furthest point, so the pressure drop is 0.63 barg, this number satisfies the needs in the end user. The measurement of the number of particles contained in compressed air, for particle of 0.3 micron reaches 170,752 particles, while for the particle size 0.5 micron reaches 45,245 particles. Measurements of particles conducted at several points of measurement. For some point measurements the number of dust particle exceeds the standard set by ISO 8573.1-2010 and also NACE Code, so it needs to be improved on the air treatment process. To see the amount of moisture content in compressed air, it is done by measuring pressure dew point temperature (PDP). Measurements were made at several points with results ranging from -28.4 to 30.9 °C. The recommendation of improving compressed air quality in steam power plant, Paiton unit 1 and 2 has the potential to extend the life of

  13. Advance in study of intelligent diagnostic method for nuclear power plant

    Zhou Gang; Yang Li

    2008-01-01

    The advance of research on the application of three types of intelligent diagnostic approach based on neural network (ANN), fuzzy logic and expert system to the operation status monitoring and fault diagnosis of nuclear power plant (NPP) was reviewed. The research status and characters on status monitoring and fault diagnosis approaches based on neural network, fuzzy logic and expert system for nuclear power plant were analyzed. The development trend of applied research on intelligent diagnostic approaches for nuclear power plant was explored. The analysis results show that the research achievements on intelligent diagnostic approaches based on fuzzy logic and expert system for nuclear power plant are not much relatively. The research of intelligent diagnostic approaches for nuclear power plant concentrate on the aspect of operation status monitoring and fault diagnosis based on neural networks for nuclear power plant. The advancing tendency of intelligent diagnostic approaches for nuclear power plant is the combination of various intelligent diagnostic approaches, the combination of neural network diagnostic approaches and other diagnostic approaches as well as multiple neural network diagnostic approaches. (authors)

  14. Feasibility Study on The Modulization of Structure and System Facility for Nuclear Power Plants

    Kim, K.S. [Korea Electric Power Research Institute, Taejon (Korea)

    2002-07-01

    This final report is a results of Study on applicable to SC(Steel Concrete) structure for NPPS and experimentation of SC wall-Support joint carried out by KEPRI from 2001.7.1 to 2000.3.27. The major objectives is to study on application of SC structure and behavior of SC wall-support joint. This result is applicable to plan a main project for ''Development of Modular Construction System in the Nuclear Power Plant''. (author). 45 refs., 19 figs., 23 tabs.

  15. A Study on Nonconformance and Construction Method Improvement for Nuclear Power Plant

    Kim, Jong Yeob; Roh, Myung Sub

    2014-01-01

    Advanced power reactor was developed by domestic technology, and finally exported to abroad. In order to place the current nuclear power industrial base, construction has played a big role. Without magnificent construction technology, it would have been impossible to get a safe nuclear power plant on time and in budget. Construction industry occupies very large portion of the economy in South Korea and it has been a core of South Korea's economic growth. With a competitive construction industry and advanced nuclear power plant construction know-how, South Korea could provide safe and reliable nuclear power plants in domestic and world. However there are many repairs and number of corrective actions are in actual construction. Thus, this paper suggested the result of nonconformance and construction method improvement for nuclear power plant. Constructional engineering is a kind of science that has a variety of disciplines including structure, geology, mechanical equipment and other fields. Thus, the development of constructional engineering is closely associated with experience from failure and application advanced construction method. The recent experience in nuclear power plants construction has shown that those improved methods are fully applicable and can help shorten the construction schedule. The future of nuclear power plant construction seems to be more encouraged, even though it has many obstacles

  16. Preliminary analysis of dry-steam geothermal power plant by employing exergy assessment: Case study in Kamojang geothermal power plant, Indonesia

    Bayu Rudiyanto

    2017-09-01

    Full Text Available The objectives of this study are to perform the exergy analysis and ambient temperature optimization of the Kamojang geothermal power plant by employing Engineering Equation Solver (EES. The geothermal capacity is 55 MW and the field is vapor-dominated reservoir with temperature 245 °C. In the initial state temperature, pressure and mass flow data are collected from the plant operation. The study results show that system has overall efficiency of 35.86% which means that only 111,138.92 kW electrical power can be extracted from 309,000 kW thermal power being produced by 10 production wells of Kamojang. This low efficiency is due to irreversibility associated with different processes and components in the system. The largest irreversibility occurs in condenser due to which 53% of total energy is disposed into the environment. Ambient temperature at Kamojang varies from 17 to 20 °C. The effect of this variation in temperature is also investigated and it is observed that higher temperature does not have any significant impact on system efficiency.

  17. Study of evaluation techniques of software safety and reliability in nuclear power plants

    Youn, Cheong; Baek, Y. W.; Kim, H. C.; Park, N. J.; Shin, C. Y. [Chungnam National Univ., Taejon (Korea, Republic of)

    1999-04-15

    Software system development process and software quality assurance activities are examined in this study. Especially software safety and reliability requirements in nuclear power plant are investigated. For this purpose methodologies and tools which can be applied to software analysis, design, implementation, testing, maintenance step are evaluated. Necessary tasks for each step are investigated. Duty, input, and detailed activity for each task are defined to establish development process of high quality software system. This means applying basic concepts of software engineering and principles of system development. This study establish a guideline that can assure software safety and reliability requirements in digitalized nuclear plant systems and can be used as a guidebook of software development process to assure software quality many software development organization.

  18. Dustfall design of open coal yard in the power plant-a case study on the closed reconstruction project of coal storage yard in shengli power plant

    Wang, Kunpeng; Ji, Weidong; Zhang, Feifei; Yu, Wei; Zheng, Runqing

    2018-02-01

    This thesis, based on the closed reconstruction project of the coal storage yard of Shengli Power Plant which is affiliated to Sinopec Shengli Petroleum Administration, first makes an analysis on the significance of current dustfall reconstruction of open coal yard, then summarizes the methods widely adopted in the dustfall of large-scale open coal storage yard of current thermal power plant as well as their advantages and disadvantages, and finally focuses on this project, aiming at providing some reference and assistance to the future closed reconstruction project of open coal storage yard in thermal power plant.

  19. Garigliano nuclear power plant

    1976-03-01

    During the period under review, the Garigliano power station produced 1,028,77 million kWh with a utilization factor of 73,41% and an availability factor of 85,64%. The disparity between the utilization and availability factors was mainly due to a shutdown of about one and half months owing to lack of staff at the plant. The reasons for nonavailability (14.36%) break down as follows: nuclear reasons 11,49%; conventional reasons 2,81%; other reasons 0,06%. During the period under review, no fuel replacements took place. The plant functioned throughout with a single reactor reticulation pump and resulting maximum available capacity of 150 MWe gross. After the month of August, the plant was operated at levels slightly below the maximum available capacity in order to lengthen the fuel cycle. The total number of outages during the period under review was 11. Since the plant was brought into commercial operation, it has produced 9.226 million kWh

  20. Mobile power plant units

    Radtke, R

    1979-10-05

    Diesel engines of the MaK line 282 AK/332 with a cylinder power up to 160 kW are used, either as 6-cylinder or 8-cylinder in-line engine or as 12-cylinder V engine. Fuel consumption is between 207 and 212 g/kW. The engine is mounted on a frame, together with a generator. The fuel reserve in the tank will last for 8 hours. The lubricating system, the cooling water and starting air system, the switchboard system, and the frame are described. The switchboard plant is mounted either on a skid undercarriage or on the undercarriage. The plant can be operated independently or parallel to the network. The unit can be remote-controlled via push buttons or control knobs. A picture is presented of a mobile diesel aggregate which is in service in Libya.

  1. A study on the development of a expert system for diagnosing fossil power plants

    Baik, Young Min; Jeong, Hee Don; Shin, Eun Ju

    2009-01-01

    In order to analyze the causes of fossil power plant facilities due to a degradation and corrosion, artificial degraded materials composed of the facilities were manufactured. Various experiment were performed based on mechanical test, microstructure observation, hardness test, Electrochemical Potentiokinetic Reactivation test (EPR) and corrosion scale thickness measurement test. The master curves were write out using Larson-Miller parameter to evaluate the degree of degradation with the above diagnosis methods. These data were applied to materials database of fossil power plant diagnosis. Finally expert system on the fossil power plant diagnosis was developed using the master curves and diagnosis algorithms.

  2. Nuclear power plant disasters

    Trott, K.R.

    1979-01-01

    The possibility of a nuclear power plant disaster is small but not excluded: in its event, assistance to the affected population mainly depends on local practitioners. Already existing diseases have to be diagnosed and treated; moreover, these physicians are responsible for the early detection of those individuals exposed to radiation doses high enough to induce acute illness. Here we present the pathogenesis, clinical development and possible diagnostic and therapeutical problems related to acute radiation-induced diseases. The differentiation of persons according to therapy need and prognosis is done on the sole base of the clinical evidence and the peripheral blood count. (orig.) [de

  3. Siting nuclear power plants

    Yellin, J.; Joskow, P.L.

    1980-01-01

    The first edition of this journal is devoted to the policies and problems of siting nuclear power plants and the question of how far commercial reactors should be placed from urban areas. The article is divided into four major siting issues: policies, risk evaluation, accident consequences, and economic and physical constraints. One concern is how to treat currently operating reactors and those under construction that were established under less-stringent criteria if siting is to be used as a way to limit the consequences of accidents. Mehanical cost-benefit analyses are not as appropriate as the systematic use of empirical observations in assessing the values involved. Stricter siting rules are justified because (1) opposition because of safety is growing: (2) remote siting will make the industry more stable; (3) the conflict is eliminated between regulatory policies and the probability basis for nuclear insurance; and (4) joint ownership of utilities and power-pooling are increasing. 227 references, 7 tables

  4. Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

    Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

    2003-04-01

    The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

  5. Pulsed nuclear power plant

    David, C.V.

    1986-01-01

    This patent describes a nuclear power plant. This power plant consists of: 1.) a cavity; 2.) a detonatable nuclear device in a central region of the cavity; 3.) a working fluid inside of the cavity; 4.) a method to denote a nuclear device inside of the cavity; 5.) a mechanical projection from an interior wall of the cavity for recoiling to absorb a shock wave produced by the detonation of the nuclear device and thereby protecting the cavity from damage. A plurality of segments defines a shell within the cavity and a plurality of shock absorbers, each connecting a corresponding segment to a corresponding location on the wall of the cavity. Each of these shock absorbers regulate the recoil action of the segments; and 6.) means for permitting controlled extraction of a quantity of hot gases from the cavity produced by the vaporization of the working fluid upon detonation of the nuclear device. A method of generating power is also described. This method consists of: 1.) introducing a quantity of water in an underground cavity; 2.) heating the water in the cavity to form saturated steam; 3.) detonating a nuclear device at a central location inside the cavity; 4.) recoiling plate-like elements inside the cavity away from the central location in a mechanically regulated and controlled manner to absorb a shock wave produced by the nuclear device detonation and thereby protect the underground cavity against damage; 5.) extracting a quantity of superheated steam produced by the detonation of the nuclear device; and 6.) Converting the energy in the extracted superheated steam into electrical power

  6. AND THERMAL POWER PLANTS

    Alduhov Oleg Aleksandrovich

    2012-10-01

    Full Text Available Investigation of the atmospheric dispersion as part of the process of selection of sites to accommodate nuclear and thermal power plants is performed to identify concentration fields of emissions and to assess the anthropogenic impact produced on the landscape components and human beings. Scattering properties of the atmospheric boundary layer are mainly determined by the turbulence intensity and the wind field. In its turn, the turbulence intensity is associated with the thermal stratification of the boundary layer. Therefore, research of the atmospheric dispersion is reduced to the study of temperature and wind patterns of the boundary layer. Statistical processing and analysis of the upper-air data involves the input of the data collected by upper-air stations. Until recently, the upper-air data covering the standard period between 1961 and 1970 were applied for these purposes, although these data cannot assure sufficient reliability of assessments in terms of the properties of the atmospheric dispersion. However, recent scientific and technological developments make it possible to substantially increase the data coverage by adding the upper-air data collected within the period between 1964 and 2010. The article has a brief overview of BL_PROGS, a specialized software package designated for the processing of the above data. The software package analyzes the principal properties of the atmospheric dispersion. The use of the proposed software package requires preliminary development of a database that has the information collected by an upper-air station. The software package is noteworthy for the absence of any substantial limitations imposed onto the amount of the input data that may go up in proportion to the amount of the upper-air data collected by upper-air stations.

  7. Wind power plant system services

    Basit, Abdul; Altin, Müfit

    Traditionally, conventional power plants have the task to support the power system, by supplying power balancing services. These services are required by the power system operators in order to secure a safe and reliable operation of the power system. However, as in the future the wind power...... is going more and more to replace conventional power plants, the sources of conventional reserve available to the system will be reduced and fewer conventional plants will be available on-line to share the regulation burden. The reliable operation of highly wind power integrated power system might...... then beat risk unless the wind power plants (WPPs) are able to support and participate in power balancing services. The objective of this PhD project is to develop and analyse control strategies which can increase the WPPs capability to provide system services, such as active power balancing control...

  8. Inventory studies of hydroelectric power plants: the methodological differences for small and large power plants; Estudos de inventario de usinas hidreletricas: as diferencas metodologicas para pequenas e grandes centrais

    Bajay, Sergio Valdir [Universidade Estadual de Campinas, SP (Brazil). Faculdade de Engenharia Mecanica. Dept. de Energia; Martinez, Carlos Barreira [Faculdade de Engenharia Civil de Itajuba, MG (Brazil)

    1992-12-31

    The hydroelectric potential handbook produced by ELETROBRAS provides procedures to guides the hydro power studies of river sites. In this paper, a critical analysis of these procedures is carried out, for both large and small hydro power plants, pin pointing the plant`s planning/design interface there, several proposals are put forward in the order to adapt these procedures to small hydro plants, optimizing their planning and design for the several situation, found in Brazilian reality. (author) 5 refs.

  9. Study on actions for social acceptance of a nuclear power plant incident/accident

    Kotani, Fumio; Tsukada, Tetsuya; Hiramoto, Mitsuru; Nishimura, Naoyuki

    1998-01-01

    When an incident/accident has occurred, dealing technically with it in an appropriate way is essential for social acceptance. One of the most important actions that are expected from the plant representative is to provide, without delay, each of the concerned authorities and organizations with full information concerning the incident/accident, while necessary technical measures are being implemented. While the importance of socially dealing with the incident/accident is widely recognized, up to now there have been no attempts to study previous incidents/accidents cases from the social sciences viewpoint. Therefore, in the present study is a case study of the incident/accident that occurred in 1991 at the No.2 Unit of the Mihama Nuclear Plant of Kansai Power Co., Ltd.. The data used in the present study is based on intensive interview of the staff involved in this incident/accident. The purpose of the study was to shed light on the conditions necessary for maintaining and improving the skill of the plant representative when dealing with social response in case of an incident/accident. The results of the present study has led to a fuller recognition of the importance of the following factors: On the personal level: 1) recognition of personal accountability, 2) complete disclosure of information concerning the incident/accident. On the organizational level: 1) acceptance of different approaches and viewpoints, 2) promoting risk-taking behavior, 3) top management's vision and commitment to providing a social response. (author)

  10. Recent progress in the feasibility study for the first nuclear power plant in Indonesia

    Subki, I.R.; Iskandar, A.; Supadi, S.

    1994-01-01

    In September 1989 the Indonesian Government decided to perform a Nuclear Power Plant feasibility study, including a comprehensive investigation of Muris site. This presentation reports on the progress to date in the two main components of this study: (a) the non-site studies, covering energy economics, financing, technical and safety aspects, the fuel cycle and waste management as well as general management aspects, and (b) site and environmental studies, covering field investigations, assessment of site selection, site qualification/evaluation, environmental, socio-economic and cultural impacts. The study is carried out under a comprehensive quality assurance programme developed by a consultancy company - NEWJEC Inc., which compiles with IAEA recommendations and was approved by BATAN. A summary of the main results, recommendations and general conclusions is presented. It is estimated that the total investment for the construction of 2 x 900 MWe or 3 x 600 MWe class Nuclear Power Plant units would be around US$7 to US$9 billion. 8 tabs

  11. Studies on the coordinated operation and autonomous control for multi-modular nuclear power plants

    Hui Chao; Huang Xiaojin; Wang Jie

    2011-01-01

    The tendency has always been to build ever larger single-modular reactor plants with the objective of benefiting from economies of scale. These plants have compiled admirable safety records. Nevertheless, there is concern that conventional large single reactors have become too complex by reason of placing too much reliance on engineered safeguards. The multi-modular approach offers a solution in that its use of many small reactors in conjunction with several shared turbines permits a simpler core design while, at the same time, at least partially retaining economies of scale by increasing the number of modules. Specific advantages to the multi-modular approach are as follows. First, the small-sized of the reactor core may allow the incorporation of passive safety features such as natural circulation cooling on loss of off-site electricity. Second, the individual modules are to be sized so that components related to nuclear safety can be factory-fabricated. Moreover, once the major components are made, they are to be transported to the site for rapid installation. This construction method is expected to reduce the licensing effort because the modules will be pre-licensed, and only site-specific issues will have to be considered in the final licensing process. At present, related studies show that the multi-modular approach for Generation IV can retain both the inherent safety and good economies of scale. However, the unbalanced load operation of the multi-modular power plant in which each module operates at a different power level and strong coupling between multi modules creates a complex control challenge to safe operation and control. Firstly, this paper summarizes the unbalanced load operation characteristics and challenges faced by operation and control of multi-modular power plant in the dynamic operational characteristics and requirements of coordinated control between multi modules. Secondly, detailed analysis and comparison are given in the integral

  12. A Comparative Study of CFD Models of a Real Wind Turbine in Solar Chimney Power Plants

    Ehsan Gholamalizadeh

    2017-10-01

    Full Text Available A solar chimney power plant consists of four main parts, a solar collector, a chimney, an energy storage layer, and a wind turbine. So far, several investigations on the performance of the solar chimney power plant have been conducted. Among them, different approaches have been applied to model the turbine inside the system. In particular, a real wind turbine coupled to the system was simulated using computational fluid dynamics (CFD in three investigations. Gholamalizadeh et al. simulated a wind turbine with the same blade profile as the Manzanares SCPP’s turbine (FX W-151-A blade profile, while a CLARK Y blade profile was modelled by Guo et al. and Ming et al. In this study, simulations of the Manzanares prototype were carried out using the CFD model developed by Gholamalizadeh et al. Then, results obtained by modelling different turbine blade profiles at different turbine rotational speeds were compared. The results showed that a turbine with the CLARK Y blade profile significantly overestimates the value of the pressure drop across the Manzanares prototype turbine as compared to the FX W-151-A blade profile. In addition, modelling of both blade profiles led to very similar trends in changes in turbine efficiency and power output with respect to rotational speed.

  13. A Study on the Safety Evaluation of Real-Time Operating System in Nuclear Power Plants

    Kim, Hyung Tae; Jeong, Choong Heui; Kim, Dail Il

    2008-01-01

    Along with the digitalisation of the nuclear Instrumentation and Control (I and C) system, Real-Time Operating System (RTOS) is being widely used. The RTOS used in nuclear I and C system should satisfy strict performance requirements and resolve various technical issues under complicated conditions. In this regard a careful safety evaluation of RTOS is important for the safety of Nuclear Power Plants. The objective of this study is to provide a guideline for safety evaluation of RTOS appropriate to the nuclear I and C system. In this paper, we suggest evaluation approach for the RTOS

  14. A Study on the Safety Evaluation of Real-Time Operating System in Nuclear Power Plants

    Kim, Hyung Tae; Jeong, Choong Heui; Kim, Dail Il [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-10-15

    Along with the digitalisation of the nuclear Instrumentation and Control (I and C) system, Real-Time Operating System (RTOS) is being widely used. The RTOS used in nuclear I and C system should satisfy strict performance requirements and resolve various technical issues under complicated conditions. In this regard a careful safety evaluation of RTOS is important for the safety of Nuclear Power Plants. The objective of this study is to provide a guideline for safety evaluation of RTOS appropriate to the nuclear I and C system. In this paper, we suggest evaluation approach for the RTOS.

  15. A study on utilization improvement of cogeneration potential in a complex industrial steam and power plant

    Mierka, O.; Variny, M.

    2012-01-01

    Efficient cogeneration is widely acknowledged as one of measures reducing primary energy use and emissions of greenhouse gases and other pollutants. This contribution bears on analyses of complex industrial power plants, incorporating the concept of exergetic and exergoecomic balances-a concept that has been rarely utilized in Slovakia up to day. Emphasis is laid on synergic use of marginal and exergoecomic analysis, thus assessing the economics of various complex cogeneration units' operational modes. The whole study, together with resulting recommendations for cogeneration efficiency improvement of the given unit is an excerpt of corresponding author's doctoral thesis. (Authors)

  16. A study on utilization improvement of cogeneration potential in a complex industrial steam and power plant

    Mierka, O.; Variny, M.

    2012-01-01

    Efficient cogeneration is widely acknowledged as one of measures reducing primary energy use and emissions of greenhouse gases and other pollutants. This contribution bears on analyses of complex industrial power plants, incorporating the concept of exergetic and exergoeconomic balances-a concept that has been rarely utilized in Slovakia up to day. Emphasis is laid on synergic use of marginal and exergoeconomic analysis, thus assessing the economics of various complex cogeneration units' operational modes. The whole study, together with resulting recommendations for cogeneration efficiency improvement of the given unit is an excerpt of corresponding author's doctoral thesis. (Authors)

  17. Study on the safety evaluation method development for D and D of Nuclear Power Plant

    Sin, S. W.; Kang, G. D.; Kim, H. S.; Son, J. G.; Choi, Y. J.; Lee, K. J.; Koh, E. O.; Kim, K. D.; Ha, J. H. [Korea Hydro and Nuclear Power Co. Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The final goal of decommissioning of Nuclear Power Plant is to remove or to isolate the radioactivity existing at the nuclear facilities which are confronted with termination of operation. The regulatory guidance and technologies of decommissioning have been developed strategically in some advanced countries. They have already stepped into the application stage from the research and development stage. The contents and the scope of this study is as follows, preparation of standard evaluation plan and establishment of standard safety evaluation system for D and D.

  18. Study on the safety evaluation method development for D and D of Nuclear Power Plant

    Sin, S. W.; Kang, G. D.; Kim, H. S.; Son, J. G.; Choi, Y. J.; Lee, K. J.; Koh, E. O.; Kim, K. D.; Ha, J. H.

    2004-02-01

    The final goal of decommissioning of Nuclear Power Plant is to remove or to isolate the radioactivity existing at the nuclear facilities which are confronted with termination of operation. The regulatory guidance and technologies of decommissioning have been developed strategically in some advanced countries. They have already stepped into the application stage from the research and development stage. The contents and the scope of this study is as follows, preparation of standard evaluation plan and establishment of standard safety evaluation system for D and D

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

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

    1993-12-15

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

  20. Study and Proposal of the Nuclear Power Plant Technology for the Ninh Thuan 2 Project

    Tran Chi Thanh; Le Van Hong; Hoang Sy Than; Nguyen Van De; Mai Dinh Trung; Nguyen Nhi Dien; Nguyen Minh Tuan; Pham Van Lam; Phan Ngoc Tuyen; Do Chi Dung; Hoang Minh Giang; Le Dai Dien

    2015-01-01

    The Ninh Thuan 1&2 Nuclear Power Plant Projects were approved on November 25th, 2009. At present, the task of NPP technology selection of these projects is an important and complex task. This report will show the acceptable method to create a set of criterion for selecting technology for Ninh Thuan 2 NPP project. The result of evaluation of three NPP technologies, such as ATMEA1, AP1000 and MPWR+ introduced in the Feasibility Study Reports of this project, will be discussed. In conclusion, the AP1000 technology is the first candidate for the Ninh Thuan 2 NPP Project. (author)

  1. Industrial safety in power plants

    1987-01-01

    The proceedings of the VGB conference 'Industrial safety in power plants' held in the Gruga-Halle, Essen on January 21 and 22, 1987, contain the papers reporting on: Management responsibility for and legal consequences of industrial safety; VBG 2.0 Industrial Accident Prevention Regulation and the power plant operator; Operational experience gained with wet-type flue gas desulphurization systems; Flue gas desulphurization systems: Industrial-safety-related requirements to be met in planning and operation; the effects of the Hazardous Substances Ordinance on power plant operation; Occupational health aspects of heat-exposed jobs in power plants; Regulations of the Industrial Accident Insurance Associations concerning heat-exposed jobs and industrial medical practice; The new VBG 30 Accident Prevention Regulation 'Nuclear power plants'; Industrial safety in nuclear power plants; safe working on and within containers and confined spaces; Application of respiratory protection equipment in power plants. (HAG) [de

  2. Estimating population exposure to power plant emissions using CALPUFF: a case study in Beijing, China

    Ying Zhou; Levy, J.I. [Harvard School of Public Health, Boston, MA (United States); Hammitt, J.K.; Evans, J.S. [Harvard Center for Risk Analysis, Boston, MA (United States)

    2003-02-01

    Epidemiological studies have shown a significant association between ambient particulate matter (PM) exposures and increased mortality and morbidity risk. Power plants are significant emitters of precursor gases of fine particulate matter. To evaluate the public health risk posed by power plants, it is necessary to evaluate population exposure to different pollutants. The concept of intake fraction (the fraction of a pollutant emitted that is eventually inhaled or ingested by a population) has been proposed to provide a simple summary measure of the relationship between emissions and exposure. Currently available intake fraction estimates from developing countries used models that look only at the near field impacts, which may not capture the full impact of a pollution source. This case study demonstrated how the intake fraction of power plant emissions in China can be calculated using a detailed long-range atmospheric dispersion model-CALPUFF. We found that the intake fraction of primary fine particles is roughly on the order of 10{sup -5}, while the intake fractions of sulfur dioxide, sulfate and nitrate are on the order of 10{sup -6}. These estimates are an order of magnitude higher than the US estimates. We also tested how sensitive the results were to key assumptions within the model. The size distribution of primary particles has a large impact on the intake fraction for primary particles while the background ammonia concentration is an important factor influencing the intake fraction of nitrate. The background ozone concentration has a moderate impact on the intake fraction of sulfate and nitrate. Our analysis shows that this approach is applicable to a developing country and it provides reasonable population exposure estimates. (author)

  3. A study of feasibility, design and cost of excavations for underground siting of nuclear power plants

    1976-02-01

    A study conducted for the State Power Board on underground siting of nuclear power plants is presented. The report is divided into two chapters, both concerning the technical aspects of large underground openings. The first chapter gives a brief general survey of the problems involved, and the second outlines the technical aspects of a PWR project at a specific site. Details are given in 8 appendices and arrangement drawings. The project differs from conventional hydroelectric excavation schemes mainly in the fact that the spherical reactor containment requires a vault of 60m free span, and the turbine hall a cylindrical vault of 45m span, both of which exceed any span hitherto built for similar purposes. This requires a comparatively wide extrapolation of tested and available experience in underground excavations for permanent civil use. To what extent and under what circumstances such extrapolation is tenable must be tested in practice, preferably in a specially controlled prototype test. However the study indicates that conventional nuclear power plants can be sited underground when the topography and rock conditions are suitable. A 1000-2000 MW conventional plant adapted for underground siting will require large span caverns, tunnels and shafts, totalling about 1.0 mill. cubic metres of underground excavation. In addition access and cooling water tunnels, depending on the location, will require 0.2-0.5 mill. cubic metres of tunnel excavations. The excavations and support work can be completed within a construction time of about 2 1/2 years at an estimated total cost of 215 mill. Norwegian kroner (1975 value). (JIW)

  4. Marine ecological habitat: A case study on projected thermal power plant around Dharamtar creek, India

    Kulkarni, V.A.; Naidu, V.S.; Jagtap, T.G.

    Estuaries and tidal creeks, harboring mangroves particularly, face tremendous anthropogenic pressures. Expansion of mega cities and the thermal power plants are generally proposed in the vicinity of estuaries and creek, due to the feasibility...

  5. Study on communicating risk information obtained from PSA within nuclear power plants

    Nunogane, Nobuaki; Onoue, Akira; Kojima, Shigeo

    2000-01-01

    In this study, the communication of PSA information in nuclear power plants (NPPs), namely, how the risk information obtained from the probabilistic safety assessment (PSA) should be presented and communicated to plant personnel, was examined assuming that the safety management system based on the risk information was introduced to NPPs. This is called PSA communication. First, when risk-informed safety management is to be introduced into NPPs, plant personnel should have sufficient related knowledge. In order to provide such knowledge to the personnel through training, risk information is classified into three types: basic information, detailed information and task information. A hierarchical risk information summary for reporting, coordinating and communicating tasks is proposed. In this summary, the concerns of those who have received the information are placed at the top and the related risk information positioned below. At the same time, and by way of a trial, the risk information relating to on-line maintenance (OLM) is prepared. In order to enhance the safety-consciousness and the safety of the entire plant, specific plans such as 'risk tags' which indicate the safety significance of equipment is proposed. Finally, a guideline providing examination procedures for developing detailed PSA communication plans is introduced. (author)

  6. Permitting a biomass-fired power plant in California -- A case study

    Reisman, J.I.; Needham, G.A.

    1995-01-01

    This paper describes the process of preparing an air permit application for a proposed biomass-fired power plant. The plant is designed to produce a net electric power output of 16 megawatts (MW) for sale to Pacific Gas and Electric Company. The biomass fuel will consist of urban wood waste, construction wood waste, and waste from agricultural products, such as tree prunings and fruit pits. The site is located in an industrial park in Soledad, California

  7. Study on the coal mixing ratio optimization for a power plant

    Jin, Y. A.; Cheng, J. W.; Bai, Q.; Li, W. B.

    2017-12-01

    For coal-fired power plants, the application of blended coal combustion has been a great issue due to the shortage and rising prices of high-rank coal. This paper describes the optimization of blending methods between Xing'an lignite coal, Shaltala lignite coal, Ura lignite coal, and Inner Mongolia bituminous coal. The multi-objective decision-making method based on fuzzy mathematics was used to determine the optimal blending ratio to improve the power plant coal-fired economy.

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

    1975-10-01

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

  9. Feasibility Study for Bioethanol Co-Location with a Coal Fired Power Plant: 29 November 2001--28 July 2002

    2002-12-01

    This study looks at the feasibility of co-locating 30, 50, and 70 million gallon per year bioethanol facilities with coal fired power plants in Indiana and Nebraska. Corn stover is the feedstock for ethanol production in both cases.

  10. The numerical and experimental study of two passes power plant condenser

    Rusowicz Artur

    2017-01-01

    Full Text Available The steam condenser is one of the most important element in whole power plant installation. Their proper design and operation makes a significant contribution to the efficiency of electricity production. The purpose of this article is to propose a two-dimensional mathematical model that allows modeling condenser work. In the model, the tube bundle is treated as a porous bed. The analysis has been subjected to a two passes power condenser with a capacity of 50 MW. The mathematical analysis was compared with the results of experimental studies. The average error between the model and the experiment for difference of cooling water temperatures was 5.15% and 11.60% for the first and second pass respectively. This allows to conclude that the proposed model is good enough to optimize future work of the condenser.

  11. Changing expectations: a longitudinal study of community attitudes toward a nuclear power plant

    Hughey, J.B.; Lounsbury, J.W.; Sundstrom, E.; Mattingly, T.J. Jr.

    1983-01-01

    Initial and 5-year follow-up interviews were conducted with 213 residents of the host community for a nuclear power plant. The purpose was to determine possible changes in attitudes toward the plant and expectations about potential outcomes associated with construction. Large negative changes in attitudes toward the plant were noted and were accompanied most notably by decreased expectations of positive outcomes. The structure of the expectations remained essentially stable over the 5-year period. Perceptions of hazards, community disruption, and economic benefits as measured early in construction and during peak construction were found to be the best predictors of acceptance of the nuclear plant. Initial expectations were found to predict overall attitude toward the plant 5 years later. Results were discussed in terms of implications for social impact assessment, large-scale community change, and the predictability of community attitudes toward nuclear power plant construction

  12. Docommissioning of nuclear power plants

    Essmann, J.

    1981-01-01

    The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

  13. Review of annual radioecological studies carried out since 1991 in the French nuclear power plants environment

    Duffa, C.; Gontier, G.; Renaud, P.

    2004-01-01

    Since 1991, the IRSN carries out annual radioecological studies in the environment of the French Nuclear Power Plants. More than 5,000 samples, collected in terrestrial and aquatic ecosystems around the 20 studied plants, have been analysed by low-level gamma spectrometry. This paper presents the main goals and methods for such studies, and the lessons learnt from 11 years results. The French NPP routine atmospheric releases do not lead to detectable radioactive inputs into their surroundings. For this reason, IRSN decided to reduce the number of analysis concerning terrestrial samples since 2000. On the other hand, NPP liquid discharges into rivers are responsible for the presence of low 60 Co, 58 Co, 110m Ag and 54 Mn activities and significant difference in 137 Cs/ 134 Cs activity ratios measured in aquatic compartments. Radioactive discharges of artificial gamma emitters are also detectable in the Channel marine environment around NPP. Nevertheless, this influence is often concealed by radionuclides released by COGEMA-La Hague nuclear reprocessing plant. Beyond important evaluations concerning the presence of artificial radionuclides in NPP's environment, studies conducted since 1991 give us an important database that can be used for a better knowledge of transfers and distribution of radioactivity through the environment. (author)

  14. A study on people's awareness about the restarting and decommissioning of nuclear power plants

    Goto, Manabu; Sakai, Yukimi

    2015-01-01

    In this study, we conducted two questionnaire surveys targeting a total of 918 respondents living in the cities of Kyoto, Osaka and Kobe, in order to elucidate people's awareness of three things: 1) restart of nuclear power plants; 2) extension of the operation period of aging plants; and 3) decommissioning. The results are as follows: 1) People who think that electrical power companies voluntarily take higher safety measures trust the power companies and do not oppose the restart of the nuclear power plants, as compared to people who think that power companies only meet the requirements set by the nuclear regulatory agency. 2) When people were given information about aging measures and conforming to new regulatory standards, their anxiety toward the operation of aging plants was reduced. 3) People thought that decommissioning work was important for society. However, a small number of people thought it was a job worthwhile doing. (author)

  15. Exploration of Compact Stellarators as Power Plants: Initial Results from ARIES-CS Study

    Najmabadi, Farrokh

    2005-01-01

    A detailed and integrated study of compact stellarators as power plants, ARIES-CS, was initiated recently to advance our understanding of attractive compact stellarator configurations and to define key R and D areas. We have completed phase 1 of ARIES-CS study - our results are described in this paper. We have identified several promising stellarator configurations. High α particle loss of these configurations is a critical issue. It appears that devices with an overall size similar to those envisioned for tokamak power plants are possible. A novel approach was developed in ARIES-CS in which the blanket at the critical areas of minimum stand-off is replaced by a highly efficient WC-based shield. In this manner, we have been able to reduce the minimum stand-off by ∼20%-30% compared to a uniform radial build which was assumed in previous studies. Our examination of engineering options indicates that overall assembly and maintenance procedure plays a critical role in identifying acceptable engineering design and has a major impact on the optimization of a plasma/coil configuration

  16. Pilot studies of management of ageing of nuclear power plant instrumentation and control components

    Burnay, S.G.; Simola, K.; Kossilov, A.; Pachner, J.

    1993-01-01

    This paper describes pilot studies which have been implemented to study the aging behavior of safety related component parts of nuclear power plants. In 1989 the IAEA initiated work on pilot studies related to the aging of such components. Four components were identified for study. They are the primary nozzle of a reactor vessel; a motor operated isolating valve; the concrete containment building; and instrumentation and control cables within the containment facility. The study was begun with phase 1 efforts directed toward understanding the aging process, and methods for monitoring and minimizing the effects of aging. Phase 2 efforts are directed toward aging studies, documentation of the ideas put forward, and research to answer questions identified in phase 1. This paper describes progress made on two of these components, namely the motor operated isolation valves, and in-containment I ampersand C cables

  17. Studies on methods and systems to improve communication between man and machine in nuclear power plants

    Bastl, W.

    1980-01-01

    The most important results of the research project are explained and analyzed: 1) Special measuring techniques for on-line control of the mechanical state of the reactor plant; 2) use of process computers for a best representation of the state of plant, for alarm condensation and for alarm analysis; 3) use of the display technique in the observatory; 4) new observatory concepts, and 5) human factors in nuclear power plants. (orig./HP) [de

  18. Feasibility study of hybrid retrofits to an isolated off-grid diesel power plant

    Rehman, S.; Ahmad, F.; Shaahid, S.M.; Shash, A.; El-Amin, I.M.; Al-Shehri, A.M.; Bakhashwain, J.M.

    2007-01-01

    The green sources of energy are being encouraged to reduce the environmental pollution and combat the global warming of the planet. A target of 12% usage of wind energy only has been agreed by the UNO country members to achieve by 2020. So, the power of the wind is being used to generate electricity both as grid connected and isolated wind-diesel hybrid power plants. This paper performed a pre-feasibility of wind penetration into an existing diesel plant of a village in north eastern part of Saudi Arabia. For simulation purpose, wind speed data from a near by airport and the load data from the village have been used. The hybrid system design tool HOMER has been used to perform the feasibility study. In the present scenario, for wind speed less than 6.0m/s the, the existing diesel power plant is the only feasible solution over the range of fuel prices used in the simulation. The wind diesel hybrid system becomes feasible at a wind speed of 6.0m/s or more and a fuel price of 0.1$/L or more. If the carbon tax is taken into consideration and subsidy is abolished then it is expected that the hybrid system become feasible. The maximum annual capacity shortage did not have any effect on the cost of energy which may be accounted for larger sizes of wind machines and diesel generators. It is recommended that the wind data must be collected at the village at three different heights using a wind mast of 40m for a minimum of one complete year and then the hybrid system must be re-designed. (author)

  19. Literature study regarding fire protection in nuclear power plants. Part 2: Fire detection and -extinguishing systems

    Isaksson, S.

    1996-01-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Detection and extinguishing systems in Swedish nuclear power plants have only to a limited extent been designed after functional demands, such as a maximum acceptable damage or a maximum time to detect a fire. The availability of detection systems is difficult to assess, partly because of lack of statistics. The user interface is very important in complex systems as nuclear plants. An extinguishing system designed according to the insurance companies' regulations will only fulfill the basic demands. It should be noted that normal sprinkler design does not aim for extinguishing fires, the objective is to control fire until manual extinguishment is possible. There is a great amount of statistics on wet and dry pipe sprinkler systems, while statistics are more scarce for deluge systems. The statistics on the reliability of gaseous extinguishing systems have been found very scarce. A drawback of these systems is that they are normally designed for one shot only. There are both traditional and more recent extinguishing systems that can replace halons. From now on there will be a greater need for a thorough examination of the properties needed for the individual application and a quantification of the acceptable damage. There are several indications on the importance of a high quality maintenance program as well as carefully developed routines for testing and surveillance to ensure the reliability of detection and extinguishing systems. 78 refs, 8 figs, 10 tabs

  20. Mortality and career radiation doses for workers at a commercial nuclear power plant: feasibility study

    Goldsmith, R.; Boice, J.D. Jr.; Hrubec, Z.; Hurwitz, P.E.; Goff, T.E.; Wilson, J.

    1989-01-01

    Career radiation doses for 8,961 male workers at the Calvert Cliffs Nuclear Power Plant (CCNPP) were determined for both utility (n = 4,960) and contractor (n = 4,001) employees. Workers were followed from the time of first employment at CCNPP (including plant construction) to the end of 1984 (mean follow-up = 5.4 y). Plant operation began in 1975. The mean duration of employment was 1.9 y at CCNPP and 3.1 y in the nuclear industry. Career radiation doses were determined from dosimetry records kept by the utility company and the U.S. Nuclear Regulatory Commission (NRC). For all exposed workers, the average career dose was 21 mSv and was higher for contractor (30 mSv) than utility (13 mSv) workers. Career doses were also higher among those employed in the nuclear industry for greater than or equal to 15 y (111 mSv) and among workers classified as health physicists (56 mSv). Cumulative doses of greater than or equal to 50 mSv were received by 12% of the workers; the maximum career dose reported was 470 mSv. The availability of social security numbers for practically all employees facilitated record-linkage methods to determine mortality; 161 deaths were identified. On average the workers experienced mortality from all causes that was 15% less than that of the general population of the U.S., probably due to healthier members of the population being selected for employment. Our investigation demonstrates that historical information is available from which career doses could be constructed and that, in principle, it is feasible to conduct epidemiologic studies of nuclear power plant workers in the U.S. Although difficult, the approach taken could prove useful until such time as a comprehensive registry of U.S. radiation workers is established

  1. RAM investigation of coal-fired thermal power plants: A case study

    D. Bose

    2012-04-01

    Full Text Available Continuous generation of electricity of a power plant depends on the higher availability of its components/equipments. Higher availability of the components/equipments is inherently associated with their higher reliability and maintainability. This paper investigates the reliability, availability and maintainability (RAM characteristics of a 210 MW coal-fired thermal power plant (Unit-2 from a thermal power station in eastern region of India. Critical mechanical subsystems with respect to failure frequency, reliability and maintainability are identified for taking necessary measures for enhancing availability of the power plant and the results are compared with Unit-1 of the same Power Station. Reliability-based preventive maintenance intervals (PMIs at various reliability levels of the subsystems are estimated also for performing their preventive maintenance (PM. The present paper highlights that in the Unit-2, Economizer (ECO & Furnace Wall Tube (FWT exhibits lower reliability as compared to the other subsystems and Economizer (ECO & Baffle Wall Tube (BWT demands more improvement in maintainability. Further, it has been observed that FSH followed Decreasing Failure Rate (DFR and Economizer (ECO is the most critical subsystem for both the plants. RAM 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.

  2. Nuclear power plants

    Ushijima, Susumu.

    1984-01-01

    Purpose: To enable to prevent the degradation in the quality of condensated water in a case where sea water leakage should occur in a steam condenser of a BWR type nuclear power plant. Constitution: Increase in the ion concentration in condensated water is detected by an ion concentration detector and the leaking factor of sea water is calculated in a leaking factor calculator. If the sea water leaking factor exceeds a predetermined value, a leak generation signal is sent from a judging device to a reactor power control device to reduce the reactor power. At ehe same tiem, the leak generation signal is also sent to a steam condenser selection and isolation device to interrupt the sea water pump of a specified steam condenser based on the signal from the ion concentration detector, as well as close the inlet and outlet valves while open vent and drain valves to thereby forcively discharge the sea water in the cooling water pipes. This can keep the condensate desalting device from ion breaking and prevent the degradation in the quality of the reactor water. (Horiuchi, T.)

  3. Study of boron behaviour in two Spanish coal combustion power plants.

    Ochoa-González, Raquel; Cuesta, Aida Fuente; Córdoba, Patricia; Díaz-Somoano, Mercedes; Font, Oriol; López-Antón, M Antonia; Querol, Xavier; Martínez-Tarazona, M Rosa; Giménez, Antonio

    2011-10-01

    A full-scale field study was carried out at two Spanish coal-fired power plants equipped with electrostatic precipitator (ESP) and wet flue gas desulfurisation (FGD) systems to investigate the distribution of boron in coals, solid by-products, wastewater streams and flue gases. The results were obtained from the simultaneous sampling of solid, liquid and gaseous streams and their subsequent analysis in two different laboratories for purposes of comparison. Although the final aim of this study was to evaluate the partitioning of boron in a (co-)combustion power plant, special attention was paid to the analytical procedure for boron determination. A sample preparation procedure was optimised for coal and combustion by-products to overcome some specific shortcomings of the currently used acid digestion methods. In addition boron mass balances and removal efficiencies in ESP and FGD devices were calculated. Mass balance closures between 83 and 149% were obtained. During coal combustion, 95% of the incoming boron was collected in the fly ashes. The use of petroleum coke as co-combustible produced a decrease in the removal efficiency of the ESP (87%). Nevertheless, more than 90% of the remaining gaseous boron was eliminated via the FGD in the wastewater discharged from the scrubber, thereby causing environmental problems. Copyright © 2011 Elsevier Ltd. All rights reserved.

  4. Exploratory study of the radiation-protection training programs in nuclear power plants

    Fields, C.D.

    1982-06-01

    The objective of the study was to examine current radiation training programs at a sample of utilities operating nuclear reactors and to evaluate employee information on radiation health. The study addressed three elements: (1) employee perceptions and understanding of ionizing radiation; (2) utility trainers-their background, training, and problems; (3) the content, materials, and conduct of training programs; (4) program uniformity and completeness. These areas were examined through visits to utilities, surveys, and employee interviews. The programs reviewed were developed by utility personnel who have backgrounds, for the most part, in health physics but who may have little formal training in adult education. This orientation, coupled with the inherent nature of the subject, has produced training programs that appear to be too technical to achieve the educational job intended. The average nuclear power plant worker does not have the level of sophistication needed to understand some of the information. It became apparent that nuclear power plant workers have concerns that do not necessarily reflect those of the scientific community. Many of these result from misunderstandings about radiation. Unfortunately, the training programs do not always address these unfounded but very real fears

  5. Environmental feasibility study for deployment and construction of mobile gas turbine power plants in urbanized areas

    Bryukhan Fedor

    2017-01-01

    Full Text Available In the view of current electrical shortage in some regions of Russia, mobile gas turbine power plants (MGTPP have become urgent in recent years. Usually they are used as back-up power sources to cover peak loads in power networks and to ensure uninterrupted power supply to consumers. This paper deals with environmental feasibility study for deployment and construction of the MGTPP in an urban setting. Technogehic factors of the MGTPP impact on the environment have been assessed and possibility of the MGTPP deployment at various sites in different regions of Russia has been identified. The necessity of using the technology of water injection into the gas turbine units combustion chamber to suppress nitrogen oxides in some cases is mentioned. Quantitative assessments of the MGTPP technogehic impact on the environment components have been performed using standard techniques. The calculations have revealed that the MGTPP specifications ensure the levels of technogehic impacts within the standard limits. The results have ensured preparation of pre-design and design documentation related to protection of the environment against the MGTPP complex technogehic impact.

  6. Hybrid combined cycle power plant

    Veszely, K.

    2002-01-01

    In case of re-powering the existing pressurised water nuclear power plants by the proposed HCCPP solution, we can increase the electricity output and efficiency significantly. If we convert a traditional nuclear power plant unit to a HCCPP solution, we can achieve a 3.2-5.5 times increase in electricity output and the achievable gross efficiency falls between 46.8-52% and above, depending on the applied solution. These figures emphasise that we should rethink our power plant technologies and we have to explore a great variety of HCCPP solutions. This may give a new direction in the development of nuclear reactors and power plants as well.(author)

  7. Accident prevention in power plants

    Steyrer, H.

    Large thermal power plants are insured to a great extent at the Industrial Injuries Insurance Institute of Instrument and Electric Engineering. Approximately 4800 employees are registered. The accident frequency according to an evaluation over 12 months lies around 79.8 per year and 1000 employees in fossil-fired power plants, around 34.1 per year and 1000 employees in nuclear power plants, as in nuclear power plants coal handling and ash removal are excluded. Injuries due to radiation were not registered. The crucial points of accidents are mechanical injuries received on solid, sharp-edged and pointed objects (fossil-fired power plants 28.6%, nuclear power plants 41.5%), stumbling, twisting or slipping (fossil-fired power plants 21.8%, nuclear power plants 19.5%) and injuries due to moving machine parts (only nuclear power plants 12.2%). However, accidents due to burns or scalds obtain with 4.2% and less a lower portion than expected. The accident statistics can explain this fact in a way that the typical power plant accident does not exist. (orig./GL) [de

  8. Effect of communication on the reliability of nuclear power plant control room operations - pre study

    Kettunen, Jari; Pyy, Pekka

    1999-01-01

    The objective of the study presented in this paper is to investigate communication practices and their impact on human reliability and plant safety in a nuclear power plant environment. The study aims at developing a general systems approach towards the issue. The ultimate goal of the study is to contribute to the development of probabilistic safety assessment methodologies in the area of communications and crew co-operation. This paper outlines the results of the pre-study. The study is based on the use and further development of different modelling techniques and the application of generic systems engineering as well as crew resource management (CRM) principles. The results so far include a concise literature review on communication and crew performance, a presentation of some potential theoretical concepts and approaches for studying communication in relation to organisational reliability, causal failure sequences and human failures mechanisms, and an introduction of a General Communications Model (GCM) that is presented as a promising approach for studying the reliability and adequacy of communication transactions. Finally, some observations and recommendation concerning next phases of the study are made (author) (ml)

  9. Study on aging management of fire protection system in nuclear power plant

    Fang Huasong; Du Yu; Li Jianwen; Shi Haining; Tu Fengsheng

    2010-01-01

    Fire prevention, fire fighting and fire automatic alarms are three aspects which be included in fire protection system in nuclear power plants. The fire protection system can protect personnel, equipment etc in the fire, so their performance will have a direct influence on the safe operation in nuclear power plants. The disabled accidents caused by aging have happened continuously with the extension of time in the fire protection system, which is the major security risk during the running time in nuclear power plants. In view of the importance of fire protection system and the severity of aging problems, the aging are highly valued by the plant operators and related organizations. Though the feedback of operating experience in nuclear power plant, the impact of the fire-fighting equipment aging on system performance and reliability be assessed, the aging sensitive equipment be selected to carry out the aging analysis and to guide the management and maintenance to guarantee the healthy operation in life time of fire protection system in nuclear power plant. (authors)

  10. Hybrid instrument applied to human reliability study in event of loss of external electric power in a nuclear power plant

    Martins, Eduardo Ferraz

    2015-01-01

    The study projects in highly complex installations involves robust modeling, supported by conceptual and mathematical tools, to carry out systematic research and structured the different risk scenarios that can lead to unwanted events from occurring equipment failures or human errors. In the context of classical modeling, the Probabilistic Safety Analysis (PSA) seeks to provide qualitative and quantitative information about the project particularity and their operational facilities, including the identification of factors or scenarios that contribute to the risk and consequent comparison options for increasing safety. In this context, the aim of the thesis is to develop a hybrid instrument (CPP-HI) innovative, from the integrated modeling techniques of Failure Mode and Effect Analysis (FMEA), concepts of Human Reliability Analysis and Probabilistic Composition of Preferences (PCP). In support of modeling and validation of the CPP-HI, a simulation was performed on a triggering event 'Loss of External Electric Power' - PEEE, in a Nuclear Power plant. The results were simulated in a virtual environment (sensitivity analysis) and are robust to the study of Human Reliability Analysis (HRA) in the context of the PSA. (author)

  11. Pre-feasibility study for an electric power plant based on rice straw. [Mali

    Fock, F. [Ea Energy Analysis, Copenhagen (Denmark); Nygaard, I. [Technical Univ. of Denmark. DTU Management Engineering, UNEP Risoe Centre on Energy, Climate and Sustainable Development, Roskilde (Denmark); Maiga, A.; Kone, B.; Kamissoko, F.; Coulibaly, N.; Ouattara, O.

    2012-11-15

    The main objective is to make a first evaluation regarding if it's technically possible, economically viable, sustainable and recommendable to build a rice straw/hulls fired power plant in Niono in Mali. Based on the available resource of rice straw and the possibilities for connecting to the grid it has been chosen to analyse a 5 MW power plant in the project. For technical reasons the rice straw should be the main fuel, but rice hulls can be used for co-firing. Up to around 20% of the fuel in the plant can be rice hulls instead of rice straw. A number of different biomass power production technologies have been evaluated in the project. This includes: 1) Grate fired boiler. 2) Bubbling fluidised bed. 3) Circulating fluidised bed. 4) Dust fired boiler. 5) Gasification. 6) Stirling engine. 7) Organic Rankine Cycle. Grate firing is the most relevant technology in this case, due to the fuel, the size of the power plant, the demand for electricity only and not heat, the demand for a robust and well proven technology. For a grate fired plant a calculation of the thermodynamic process of the power plant has been carried out in order to determine the electrical efficiency of the plant. The case consists of a 5 MW grate fired power plant with steam turbines and air cooled condenser resulting in an efficiency of 24.6% at full load (20% as yearly average). Investment costs and costs for O and M have been assumed based on experience from Danish power plants but adjusted for local conditions in Mali. The costs for collecting and transporting the rice straw and for the ash disposal have been specifically estimated in this project. The average cost of capital has been estimated based on assumptions on equity, international loans and local loans/bank finance. Based on the investment, the cost of O and M, fuel, ash disposal and the financial assumptions, a cash flow analysis is made in order to calculate the power price resulting in a Net Present Value (NPV) of the

  12. Wuergassen nuclear power plant

    Anon.

    1989-01-01

    The decision of the Federal Court of Administration concerns an application for immediate decommissioning of a nuclear power plant (Wuergassen reactor): The repeal of the permit granted. The decision dismisses the appeal for non-admission lodged by the plaintiffs against the ruling of the Higher Court of Administration (OVG) of North-Rhine Westphalia of December 19th 1988 (File no. 21 AK 8/88). As to the matter in dispute, the Federal Court of Administration confirms the opinion of the Higher Court of Administration. As to the headnotes, reference can be made to that decision. Federal Court of Administration, decision of April 5th 1989 - 7 B 47.89. Lower instance: OVG NW, Az.: 21 AK 8/88. (orig./RST) [de

  13. Nuclear power plant

    Uruma, Hiroshi

    1998-01-01

    In the first embodiment of the present invention, elements less activated by neutrons are used as reactor core structural materials placed under high neutron irradiation. In the second embodiment of the present invention, materials less activated by neutrons when corrosive materials intrude to a reactor core are used as structural materials constituting portions where corrosion products are generated. In the third embodiment, chemical species comprising elements less activated by neutrons are used as chemical species to be added to reactor water with an aim of controlling water quality. A nuclear power plant causing less radioactivity can be provided by using structural materials comprising a group of specific elements hardly forming radioactivity by activation of neutrons or by controlling isotope ratios. (N.H.)

  14. Nuclear power plant

    Schabert, H.P.

    1976-01-01

    A nuclear power plant is described which includes a steam generator supplied via an input inlet with feedwater heated by reactor coolant to generate steam, the steam being conducted to a steam engine having a high pressure stage to which the steam is supplied, and which exhausts the steam through a reheater to a low pressure stage. The reheater is a heat exchanger requiring a supply of hot fluid. To avoid the extra load that would be placed on the steam generator by using a portion of its steam output as such heating fluid, a portion of the water in the steam generator is removed and passed through the reheater, this water having received at least adequate heating in the steam generator to make the reheater effective, but not at the time of its removal being in a boiling condition

  15. A Study on Guidelines for the Utilization of Unproven MMIS Technology In Nuclear Power Plant Application

    Kang, Sung Kon; Shin, Yeong Cheol; Bae, Byoung Hwan

    2007-01-01

    New MMIS (Man Machine Interface System) technology is rapidly advanced as digital technology provides opportunity for more functionality and better cost effectiveness and NPP (Nuclear Power Plant) operators are inclined to use the new technology for the construction of new plant and for the upgrade of existing plants. However, this new technology poses risks to the NPP operators at the same time. These risks are mainly due to the poor reliability of newly developed technology. KHNP's past experiences with the new MMIS equipment shows many cases of reliability problem. And their consequences include unintended plant trips, lowered acceptance of the new digital technology by the plant I and C maintenance crew, and increased licensing burden in answering for questions from the nuclear regulatory body. Considering the fact that the risk of these failures in the nuclear plant operation is far greater than those in other industry, utilities require proven technology for the MMIS in nuclear power plants. So that new MMIS technology might be testified as proven technology, guidelines for the utilization of unproven MMIS technology in nuclear power plant application is required for applying new advanced MMIS technology which is apparently needed to obtain a definite gain in simplicity or performance

  16. A Study on Establishment of Nuclear Power Plant Technical Support System and Activation Plan

    Wi, M. H.; Park, W. S.; Lee, H. S.; Kim, J. H.; Won, B. C.; Kim, Y. H.; Goo, D. S.; Choi, H. B.

    2009-11-01

    This report includes activities related to establishment of 'BaroBaro nuclear plant technical support center', 'selection of nuclear plant applicable technology', and 'various information interchange between KAERI and nuclear power plant'. 'BaraBaro center was newly organized to support on resolving the technical difficulties in operation of nuclear power plant'. The center consists of 10 technical parts and a leading expert is assigned to each part to support more efficiently. This center is always served for 24 hour. The plant operators can register their problem to the center by a call, e-mail, or internet and they can receive the answer about what they issued from KAERI experts. To make a brochure, we selected 32 technologies which are applicable in nuclear plant without additional R and D activity. The brochure was distributed to the officer in charge of nuclear plant operations. Various meetings were held to increase interchange of experience and technology between KAERI and nuclear power plant and we discussed many different issues at that meeting

  17. Study on the operational safety performance indicator of nuclear power plants in China

    Zhou Shirong

    2005-01-01

    The operational Safety Performance Indicator system (SPI) has been more and more regarded recently for their clear and effective characteristic in safety assessment for Nuclear Power Plants (NPPs). A large developing plan for NPPs construction is being discussed and considered in P.R. China. As one of important nuclear country, China expects to ensure the normal operation of NPPs and improve the safety level. National Nuclear Safety Administration (NNSA), National Nuclear Regulatory Agency of China, has put high attention on safety and SPI area, and many endeavours and attempts have been done or being carried out for an establishment of SPI system in China. NNSA intends to build an integrated SPI system to monitor all of the NPPs operation in China, based on the SPI system currently used in the world. NNSA believes that the SPI system will help to more effectively enforce the function of surveillance and management. The paper will introduces the status of study on the operational safety performance indicator of Nuclear Power Plants in China. (author)

  18. A study in the reliability analysis method for nuclear power plant structures (I)

    Oh, Byung Hwan; Choi, Seong Cheol; Shin, Ho Sang; Yang, In Hwan; Kim, Yi Sung; Yu, Young; Kim, Se Hun [Seoul, Nationl Univ., Seoul (Korea, Republic of)

    1999-03-15

    Nuclear power plant structures may be exposed to aggressive environmental effects that may cause their strength and stiffness to decrease over their service life. Although the physics of these damage mechanisms are reasonably well understood and quantitative evaluation of their effects on time-dependent structural behavior is possible in some instances, such evaluations are generally very difficult and remain novel. The assessment of existing steel containment in nuclear power plants for continued service must provide quantitative evidence that they are able to withstand future extreme loads during a service period with an acceptable level of reliability. Rational methodologies to perform the reliability assessment can be developed from mechanistic models of structural deterioration, using time-dependent structural reliability analysis to take loading and strength uncertainties into account. The final goal of this study is to develop the analysis method for the reliability of containment structures. The cause and mechanism of corrosion is first clarified and the reliability assessment method has been established. By introducing the equivalent normal distribution, the procedure of reliability analysis which can determine the failure probabilities has been established. The influence of design variables to reliability and the relation between the reliability and service life will be continued second year research.

  19. Study of candu fuel elements irradiated in a nuclear power plant

    Ionescu, S.; Uta, O.; Mincu, M.; Anghel, D.; Prisecaru, I.

    2015-01-01

    The object of this work is the behaviour of CANDU fuel elements after service in nuclear power plant. The results are analysed and compared with previous result obtained on unirradiated samples and with the results obtained on samples irradiated in the TRIGA reactor of INR Pitesti. Zircaloy-4 is the material used for CANDU fuel sheath. The importance of studying its behaviour results from the fact that the mechanical properties of the CANDU fuel sheath suffer modifications during normal and abnormal operation. In the nuclear reactor, the fuel elements endure dimensional and structural changes as well as cladding oxidation, hydriding and corrosion. These changes can lead to defects and even to the loss of integrity of the cladding. This paper presents the results of examinations performed in the Post Irradiation Examination Laboratory (PIEL) of INR Pitesti on samples from fuel elements after they were removed out of the nuclear power plant: - dimensional and macrostructural characterization; - microstructural characterization by metallographic analyses; - determination of mechanical properties; - fracture surface analysis by scanning electron microscopy (SEM). A full set of non-destructive and destructive examinations concerning the integrity, dimensional changes, oxidation, hydriding and mechanical properties of the cladding was performed. The obtained results are typical for CANDU 6-type fuel. The obtained data could be used to evaluate the security, reliability and nuclear fuel performance, and for the improvement of the CANDU fuel. (authors)

  20. Birth Outcomes after the Fukushima Daiichi Nuclear Power Plant Disaster: A Long-Term Retrospective Study

    Leppold, Claire; Nomura, Shuhei; Sawano, Toyoaki; Ozaki, Akihiko; Tsubokura, Masaharu; Hill, Sarah; Kanazawa, Yukio; Anbe, Hiroshi

    2017-01-01

    Changes in population birth outcomes, including increases in low birthweight or preterm births, have been documented after natural and manmade disasters. However, information is limited following the 2011 Fukushima Daiichi Nuclear Power Plant Disaster. In this study, we assessed whether there were long-term changes in birth outcomes post-disaster, compared to pre-disaster data, and whether residential area and food purchasing patterns, as proxy measurements of evacuation and radiation-related anxiety, were associated with post-disaster birth outcomes. Maternal and perinatal data were retrospectively collected for all live singleton births at a public hospital, located 23 km from the power plant, from 2008 to 2015. Proportions of low birthweight (increased proportions of low birthweight or preterm births in any year after the disaster (merged post-disaster risk ratio of low birthweight birth: 0.98, 95% confidence interval (CI): 0.64–1.51; and preterm birth: 0.68, 95% CI: 0.38–1.21). No significant associations between birth outcomes and residential area or food purchasing patterns were identified, after adjustment for covariates. In conclusion, no changes in birth outcomes were found in this institution-based investigation after the Fukushima disaster. Further research is needed on the pathways that may exacerbate or reduce disaster effects on maternal and perinatal health. PMID:28534840

  1. A Study on Introduction of Nuclear Power Plants in India and the Nuclear Non- Proliferation Conditions

    Yang, Seung Hyo; Lim, Dong Hyuk

    2011-01-01

    Nuclear Suppliers Group (NSG) which was formed to build nuclear export control has been accepting the nuclear cooperation for the member nation of the international nuclear non-proliferation regime. Korea exported nuclear power plants to United Arab Emirates in 2009 and research and training reactor to Jordan in 2010 based on the forcible non-proliferation regime as a member nation of NSG, so it is strengthening its position in the atomic energy industry. In addition, Korea concluded an agreement with India which is planning the construction of 25.based or more nuclear power plants for the next 20 years in last July, 25, so it will enter the atomic energy market in India. But India has been accepted the exceptionally civilian nuclear cooperation as a de facto Nuclear Weapon State (NWS) and non-member state of NPT, so concerns about nuclear proliferation has been raised. This study aims to introduce the allowance of exceptions background in India, to analyze its effect on the non-proliferation regime and to find nuclear non-proliferation conditions

  2. White syndrome on massive corals: A case study in Paiton power plant, East Java

    Muzaki, Farid Kamal; Saptarini, Dian; Riznawati, Aida Efrini

    2017-06-01

    As a stenothermal organism, coral easily affected by high-temperature cooling water discharged by a power plant into surrounding waters; which may lead to a rapid spread and transmission of coral disease, including White Syndrome. This study aimed to measure the prevalence of WS on massive corals in Paiton Power Plant waters. Research was conductedduring May 2015 at three observation stations; west and east side of water discharge canal (DB and DT) and water intake canal (WI). Observed parameters including ambient environmental variables (sea surface and bottom temperature, salinity, dissolved oxygen/DO, pH, and visibility); the cover of life corals (percent and genera composition) and prevalence of coral disease at 5 m depth. One-way ANOVA (analysis of variance, p=0.05) was performed to test the difference of coral disease prevalence from different observation stations. As the results, Coral coverage percentage in WI (85.75%), DB (60.75%), and DT (40.8%). Prevalence of WS in DB was highest (40.49±2.12% in DB, 13.53±11.5% in DT and 6.44±3.6 %, respectively). It can be assumed that prevalence of White Syndrome in those locations may be correlated to temperature which highest average temperature occurred in DB stations.

  3. Power plant removal costs

    Ferguson, J.S.

    1998-01-01

    The financial, regulatory and political significance of the estimated high removal costs of nuclear power plants has generated considerable interest in recent years, and the political significance has resulted in the Nuclear Regulatory Commission (NRC) eliminating the use of conventional depreciation accounting for the decontamination portion of the removal (decommissioning). While nuclear plant licensees are not precluded from utilizing conventional depreciation accounting for the demolition of non-radioactive structures and site restoration, state and federal utility regulators have not been favorably inclined to requests for this distinction. The realization that steam-generating units will be more expensive to remove, relative to their original cost, predates the realization that nuclear units will be expensive. However, the nuclear issues have overshadowed this realization, but are unlikely to continue to do so. Numerous utilities have prepared cost estimates for steam generating units, and this presentation discusses the implications of a number of such estimates that are a matter of public record. The estimates cover nearly 400 gas, oil, coal and lignite generating units. The earliest estimate was made in 1978, and for analysis purposes the author has segregated them between gas and oil units, and coal and lignite units

  4. Perspectives of nuclear power plants

    Vajda, Gy.

    2001-01-01

    In several countries the construction of nuclear power plants has been stopped, and in some counties several plants have been decommissioned or are planned to. Therefore, the question arises: have nuclear power plants any future? According to the author, the question should be reformulated: can mankind survive without nuclear power? To examine this challenge, the global power demand and its trends are analyzed. According to the results, traditional energy sources cannot be adequate to supply power. Therefore, a reconsideration of nuclear power should be imminent. The economic, environmental attractions are discussed as opposite to the lack of social support. (R.P.)

  5. Study on the possible consequences of a severe accident in a Swiss nuclear power plant on the drinking water supply

    Ustohalova, Veronika; Kueppers, Christian; Claus, Manuel

    2014-01-01

    The study on the possible consequences of a severe accident in a Swiss nuclear power plant on the drinking water supply covers the following issues: estimation of possible source terms and radioactive materials release rates, airborne water contamination, water contamination by direct pollution, consequences for the drinking water supply, emergency measures in case of a drinking water contamination, routine surveillance of surface and ground water and improvement possibilities in nuclear power plants.

  6. A comparative study among fossil fuel power plants in PJM and California ISO by DEA environmental assessment

    Sueyoshi, Toshiyuki; Goto, Mika

    2013-01-01

    This study compares among fossil fuel power plants in PJM and California ISO by their unified (operational and environmental) performance. DEA (Data Envelopment Analysis) is used as a methodology. For comparative analysis, DEA incorporates strategic concepts such as natural and managerial disposability into the computational process. This study explores both how to measure Returns to Scale (RTS) under natural disposability and how to measure Damages to Scale (DTS) under managerial disposability. This empirical study obtains two implications on US energy policy. One of the two policy implications is that California ISO outperforms PJM in terms of the three unified efficiency measures. The result implies that strict regulation on undesirable outputs, as found in California, is important in enhancing the performance of US fossil fuel power plants. Thus, it is necessary for federal and local governments to regulate the fossil fuel power plants under the strict implementation of environmental protection. Under such a policy direction, it is possible for US fossil fuel power plants to attain economic prosperity (by enhancing their operational efficiencies) and to satisfy environmental regulation (by enhancing their environmental efficiencies). The other policy implication is that coal-fired and gas-fired power plants in PJM and California ISO need to reduce their operational sizes or introduce technology innovation on desirable and undesirable outputs and/or new management for environmental protection within their operations. Meanwhile, oil-fired power plants may increase their operational sizes if they can introduce technology innovation and new management on undesirable outputs. - Highlights: • This study compares fossil fuel power plants in PJM and California ISO. • California ISO outperforms PJM in terms of their unified efficiency measures. • Regulation by Clean Air Act is important for environmental protection. • Fossil fuel power plants need technology

  7. Summary and evaluation of the conceptual design study of a potential early commercial MHD power plant (CSPEC)

    Staiger, P. J.; Penko, P. F.

    1982-01-01

    The conceptual design study of a potential early commercial MHD power plant (CSPEC) is described and the results are summarized. Each of two contractors did a conceptual design of an approximtely 1000 MWe open-cycle MHD/steam plant with oxygen enriched combustion air preheated to an intermediate temperatue in a metallic heat exchanger. The contractors were close in their overall plant efficiency estimates but differed in their capital cost and cost of electricity estimates, primarily because of differences in balance-of-plant material, contingency, and operating and maintenance cost estimates. One contractor concluded that its MHD plant design compared favorably in cost of electricity with conventional coal-fired steam plants. The other contractor is making such a comparison as part of a follow-on study. Each contractor did a preliminary investigation of part-load performance and plant availability. The results of NASA studies investigating the effect of plant size and oxidizer preheat temperature on the performance of CSPEC-type MHD plants are also described. The efficiency of a 1000 MWe plant is about three points higher than of a 200 MWe plant. Preheating to 1600 F gives an efficiency about one and one-half points higher than preheating to 800 F for all plant sizes. For each plant size and preheat temperature there is an oxidizer enrichment level and MHD generator length that gives the highest plant efficiency.

  8. Safety probabilistic study of Almirante Alvaro Alberto nuclear power plant-Unit I

    Lederman, L.; Arrieta, L.A.I.; Fernandes Filho, T.L.; Gibelli, S.M.O.; Berthoud, J.S.; Ambros, P.C.; Soares, H.V.; Camargo, C.T.M.

    1985-04-01

    The phase A of probabilistic safety study of Angra I nuclear power plant is presented, to be used by CNEN and FURNAS Centrais Eletricas S.A. as standard model in operational and safety analysis. The methodology applied is a modernization of WASH 1400/2.11/ study. Angra I safety systems are described. The selection and qualification of initiating sequence accident events which can damage the reactor core are done. The accident scenes are developed using the method of event trees. The reactor in subcritical condition (pressure, fuel temperature within limits and controlled level of reactor vessel) is studied during 24 hours. The uncertainness in failure probabilities of systems and in the determination of sequence frequencies for core danification are evaluated. Total frequency of sequences which cause the fusion of reactor core are presented. (M.C.K.) [pt

  9. Loss-of-benefits analysis for nuclear power plant shutdowns: methodology and illustrative case study

    Peerenboom, J.P.; Buehring, W.A.; Guziel, K.A.

    1983-11-01

    A framework for loss-of-benefits analysis and a taxomony for identifying and categorizing the effects of nuclear power plant shutdowns or accidents are presented. The framework consists of three fundamental steps: (1) characterizing the shutdown; (2) identifying benefits lost as a result of the shutdown; and (3) quantifying effects. A decision analysis approach to regulatory decision making is presented that explicitly considers the loss of benefits. A case study of a hypothetical reactor shutdown illustrates one key loss of benefits: net replacement energy costs (i.e., change in production costs). Sensitivity studies investigate the responsiveness of case study results to changes in nuclear capacity factor, load growth, fuel price escalation, and discount rate. The effects of multiple reactor shutdowns on production costs are also described

  10. Health state of population in vicinity of the Mochovce nuclear power plant. Epidemiologic study

    Celko, M.; Durov, M.; Letkovicova, M.; Holy, R.; Sedliak, D.; Zrubec, M.; Kristufek, P.; Machata, M.; Prikazsky, V.; Rehak, R.; Stehlikova, B.; Vladar, M.

    1999-01-01

    Results of epidemiologic study of health state of population in vicinity of the Mochovce nuclear power plant (Slovak Republic) are presented. This report is reported under the headings: (1) Introduction; (2) Basic information about Mochovce NPP; (3) Assessment of population exposition by environmental factors; (4) Basic conceptions and principles of epidemiologic study; (5) Demography and health state of population; (6) Characterisation of databases and data; (7) Description of demographic and health indicators; (8) Calculation of demographic and health indicators in vicinity of the Mochovce NPP and in control areas; (9) Calculated indicators; (10) Statistical methods and evaluation of calculated indicators; (11) Summary and conclusions; (12) References; Appendixes: Literature review of similar epidemiologic studies; Quantities and units in radiation protection; Definitions of indicators calculation - specification of method

  11. Study of the energy matrix of Minas Gerais considering the contribution of nuclear power plants

    Filho, Wilson P.B., E-mail: wilson.filho@meioambiente.mg.gov.br [Fundaco Estadual do Meio Ambiente, Belo Horizonte, MG (Brazil); Costa, Antonella L.; Pinheiro, Ricardo B.; Fortini, Angela, E-mail: antonella@nuclear.ufmg.br, E-mail: rbrantp@gmail.com, E-mail: fortini@nuclear.ufmg.br [Universidade Federal de Minas Gerais (UFMG), Belo horizonte, MG (Brazil). Departamento de Engenharia Nuclear

    2015-07-01

    The integrated energy planning is a very important tool for long-term study, projections and reviews of the energy mix of a country or region. By dealing with energy supply and demand projections is therefore related to the needs of society and its development index within a context of sustainability. The aim of this study is to provide information about the Minas Gerais electric matrix and propose solutions for the need of future energy import. In this way, it is proposed a possible deployment of nuclear power plants, in parallel with wind and solar energy, for the necessary energy expansion in the face of population growth framework and energy use in Minas Gerais. Thus, the study tends to contribute to decision-making related to public policies. (author)

  12. Study of the energy matrix of Minas Gerais considering the contribution of nuclear power plants

    Filho, Wilson P.B.; Costa, Antonella L.; Pinheiro, Ricardo B.; Fortini, Angela

    2015-01-01

    The integrated energy planning is a very important tool for long-term study, projections and reviews of the energy mix of a country or region. By dealing with energy supply and demand projections is therefore related to the needs of society and its development index within a context of sustainability. The aim of this study is to provide information about the Minas Gerais electric matrix and propose solutions for the need of future energy import. In this way, it is proposed a possible deployment of nuclear power plants, in parallel with wind and solar energy, for the necessary energy expansion in the face of population growth framework and energy use in Minas Gerais. Thus, the study tends to contribute to decision-making related to public policies. (author)

  13. A study of a small nuclear power plant system for district heating

    Imamura, Mitsuru; Sato, Kotaro; Narabayashi, Tadashi; Shimazu, Yoichiro; Tsuji, Masashi

    2008-01-01

    We have studied nuclear power plant for district heating. Already some towns and villages in Hokkaido have requested small reactor for district heating. Using existing technology allows us to shorten development period and to keep a lid on development cost. We decided to develop new reactor based on 'MUTSU' reactor technology. 'MUTSU' had already proved its safety. And 'MUTSU' reactor was boron free reactor. It allows plant system to become more compact and simple. And load following capability by core reactivity become bigger. It means to reduce control rod movement. It leads to dependability enhancement. We calculated burn-up calculation of erbium addition fuel. In the result the core life became about 10 years. In the district heating system, there are not only district heating but also snow melting with warm water. It uses steam condenser's heat, which are only discharged now. This small plant has passive safety system. It is natural cooling of containment vessel. In case of loss of coolant accident, decay heat can remove by natural convection air cooling after 6 hours. Decay heat within 6 hours can remove by evaporative heat transfer of pool on containment vessel. (author)

  14. Wind-power plant

    Kling, A

    1976-08-26

    The invention is concerned with a wind-power plant whose rotor axis is pivoted in the supporting structure and swingable around an axis of tilt, forming an angle with the rotor axis and the vertical axis, and allowing precession of the rotor. On changes of wind direction an electric positioning device is moving the rotor axis into the new direction in such a way that no precession forces are exerted on the supporting structure and this one may very easily be held. Instead of one rotor, also a type with two coaxial, co-planar countercurrent rotors may be used. Each of the two countercurrent rotors is carrying a number of magnetic poles, distributed all over the circumference, acting together with the magnetic poles of the other rotor. At least the poles of one rotor have electric line windings being connected by leads with a collector so that the two rotors form the two parts of a power generator being each rotatable with respect to the other ('stator' and 'rotor').

  15. Study on public awareness of utilizing nuclear power in China. Changes in public awareness after the accident of Fukushima Daiichi Nuclear Power Plants

    Xu, Ting; Wakabayashi, Toshio

    2012-01-01

    The purpose of this study is to clarify public awareness of utilizing nuclear power in China and to determine the effects of the accident of Fukushima Daiichi nuclear power plants. Web online surveys were carried out before and after the accident of Fukushima Daiichi nuclear power plants. The online survey before the accident of Fukushima Daiichi nuclear power plants had 4,255 adult respondents consisting of 1,851 males and 2,404 females. The online survey after the accident had 721 respondents consisting of 406 males and 315 females. The two online surveys about the attitude toward nuclear power plants consisted of 37 items, such as the necessity of nuclear power plants, the reliability of safety, and government confidence. As a result, respondents of the online surveys in China consider that nuclear energy is more important than the anxiety of accident. On the other hand, women have sensation of fear for the accident of Fukushima Daiichi nuclear power plants and radiation. (author)

  16. Power generation by nuclear power plants

    Bacher, P.

    2004-01-01

    Nuclear power plays an important role in the world, European (33%) and French (75%) power generation. This article aims at presenting in a synthetic way the main reactor types with their respective advantages with respect to the objectives foreseen (power generation, resources valorization, waste management). It makes a fast review of 50 years of nuclear development, thanks to which the nuclear industry has become one of the safest and less environmentally harmful industry which allows to produce low cost electricity: 1 - simplified description of a nuclear power generation plant: nuclear reactor, heat transfer system, power generation system, interface with the power distribution grid; 2 - first historical developments of nuclear power; 3 - industrial development and experience feedback (1965-1995): water reactors (PWR, BWR, Candu), RBMK, fast neutron reactors, high temperature demonstration reactors, costs of industrial reactors; 4 - service life of nuclear power plants and replacement: technical, regulatory and economical lifetime, problems linked with the replacement; 5 - conclusion. (J.S.)

  17. Study of Formosa's electrical offer for installing a commercial nuclear power plant

    Torino Araoz, Ines; Parera, Maria D.

    2011-01-01

    Within the specific agreement for the siting study of the CAREM nuclear power plant in Formosa Province, signed between the National Atomic Energy Commission and the Government of Formosa, a detailed study of electrical supply was conducted in order to analyze the requirements and the electricity supply as a result of its future installation. This topic is part of the analysis developed in the Level II of the site survey study. The analysis focuses on a plan for long-term projections from 2005 to 2030, using the IAEA’s MESSAGE model (Model for Energy Supply Strategy Alternatives and Their General Environmental Impacts). The existing electrical infrastructure and the plans for expansion of transmission and distribution lines, the generation technologies and the electricity flows with the provinces and neighboring countries have been taken into account. The study was based on the evaluation of two site scenarios based on the availability of infrastructure in the province and the conclusions obtained in the Level I of the siting study. The modelling results indicate that the current situation that characterizes the Province as a net importer of electricity will be reversed due to the operation of the nuclear plant since 2019. However, it is important to note that to keep Formosa’s feature as an electricity exporter from the year 2026, according to the less favorable scenario (highest demand), ongoing energy planning and investment in the province will be done. (author) [es

  18. Study on the selection method of feed water heater safety valves in nuclear power plants

    Shi Jianzhong; Huang Chao; Hu Youqing

    2014-01-01

    The selection of the high pressure feedwater heater's safety valve usually follows the principle recommended by HEI standards in thermal power plant. However, the nuclear power plant's heaters generally need to accept a lots of drain from a moisture separator reheater (MSR). When the drain regulating valve was failure in fully open position, a large number of high pressure steam will directly goes into the heater. It make high-pressure heater have a risk of overpressure. Therefore, the safety valve selection of the heaters for nuclear power plants not only need to follow the HEI standards, but also need to check his capacity in certain special conditions. The paper established a calculation method to determine the static running point of the heaters based on characteristic equations of the feed water heater, drain regulating valve and steam extraction pipings, and energy balance principle. The method can be used to calculate the equilibrium pressure of various special running conditions, so further determine whether the capacity of the safety valve meets the requirements of safety and emissions. The method proposed in this paper not only can be used for nuclear power plants, can also be used for thermal power plants. (authors)

  19. Studies of safety and critical work situations in nuclear power plants: A human factors perspective

    Jacobsson Kecklund, L.

    1998-05-01

    The purpose of this thesis was to develop and apply different approaches for analyzing safety in critical work situations in real work settings in nuclear power plants, and also to identify safety enhancing measures by using the framework of interaction between human, organizational and technical subsystems. A Cognitive Psychology as well as a Stress Psychology framework was used. All studies were related to the annual outage operational state where the need for coping with many infrequent tasks, often carried out under high time pressure, puts great strain on the staff and organisation of the plant. In three studies the natural variations in the plant state, normal operation and annual outage operation, were used to explore human performance, work-related factors as well as coping and the operators' own resources and the relationship between them. In the annual outage condition high work demands, decreased sleepiness at night shift, more errors and less satisfaction with work performance quality was reported by maintenance as well as by control room operators. A relationship between high work demands and more organizational problems and reports of more frequent human errors and lower satisfactions with work performance quality was also identified in the annual outage condition. Moreover, a relationship between increased sleepiness during night shift, more frequent use of coping strategies and a higher frequency of human errors was reported. In two studies the Event and Barrier Function Model was applied to analyze the safety of barrier function systems inserted into work process sequences to protect the systems from the negative consequences of failures and errors. The model was also used to assess safety in relation to a technical and organizational change. The last study addressed changes in work performance and work-related factors in relation to a technical and organizational change of a safety significant work process involving increased automation and new

  20. Public perception on the benefits and risks of nuclear power plants. A simplified study

    Ribeiro Junior, Joaquim Apparecido

    2007-01-01

    Public acceptance of the nuclear based electricity generation depends on many variables that can be affected by circumstances and interests, which although seemingly not close to the issue, can strongly influence the final outcome. Explicit or consented positions assumed by opinion makers and some segments of society are subject to episodic waves of interaction through the media and they permeate to the public in a process that is very complex to be fully understood. The modeling of such process is a very complicated undertaking, and gives no assurance of practical results concerning to what, how and who, should be given prominence in the interactions with the media and the general public. In this context, the risk communication has assumed a leading role and, as a consequence, most of the interaction with the public has been done with both defensive language and content. This study has tried a simple and practical approach to the problem, in such a way as to gather some interesting subsidies to treat this issue in a different way. The basic assumption is that in a similar way as individuals base their decision to acquire a new good or service on a 'intuitive' cost-benefit judgment, society (as a collection of individuals) also manifest their acceptance (or not) with respect to industrial installations and undertakings by comparing risks and benefits according to their perception. An exploratory survey was carried out in a few high schools, colleges and MBA courses in the state of Sao Paulo, Brazil. A first part was aimed to catch and understand the public perception of: the intrinsic value of the electric energy, the need to universalize the access to electricity, nuclear plants, the acceptance deficit of nuclear power as compared to other sources of energy, the benefits a nuclear plant can bring and who does and who does not deserves credibility to speak about nuclear plants. The second part was addressed to grasp a picture of more relevant distortions concerned

  1. A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

    Yang, Chih Wei; Yang, Li Chen [Institute of Nuclear Energy Research, Atomic Energy Council, Longtan (China)

    2014-08-15

    Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective.

  2. A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

    Yang, Chih Wei; Yang, Li Chen

    2014-01-01

    Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective

  3. Burn cycle study of tokamak power plants by the Effective Management Method

    Okano, Kunihiko; Inoue, Nobuyuki; Ogawa, Yuichi; Yoshida, Zensho

    1995-01-01

    The Effective Management Method is an action decision manner to work out the strategy of enterprises, which was developed in Japan on the base of the Kepner and Trigoe Method developed in the USA. The authors applied this method with a small modification to a burn cycle study of tokamak power plants. The numerical figure of merit for the pulsed and steady state operations are visually shown. Steady state, 1 hour pulse (with and without energy reservoir) and half-day long pulse reactor are compared. The EM method provides a common base for such comparing study. The highest score is given to an 1 hour pulsed operated reactor with an energy reservoir for the continuous electric output. However it is also pointed out that there is no 'significant' superiority in both of the steady state and pulse reactors. (author)

  4. Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

    Woo, Tae Ho, E-mail: thw@snu.ac.kr

    2013-12-15

    Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs.

  5. Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

    Woo, Tae Ho

    2013-01-01

    Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs

  6. Study on information dissemination regarding trouble at a nuclear power plant

    Ueda, Yoshitaka

    2007-01-01

    We conducted a survey concerning how the general public perceived information regarding trouble that occurred at a nuclear power plant, and what kind of information people wished to obtain regarding such trouble. We then identified the points to be aware of in the future when disseminating such information. The results showed that people preferred such information to be disseminated not only via mass media, but also by governments and nuclear power plant companies. The results also revealed that terms used in explaining nuclear power plant troubles were not well known to the general public. Even some terms used to demonstrate safety to the public might only cause concern. We also learned that some information issued directly to the general public by electric power companies was difficult to understand, and that such information can give people a more serious image than the actual trouble. We therefore conducted interviews with the general public to collect opinions directly regarding points to be improved to ensure that information on nuclear power plant troubles is easy to understand and not misleading. We then actually prepared several patterns of trouble information by adding improvements on the basis of the collected opinions, and conducted a comparative review of these patterns. The results showed that ease of understanding of such information can be improved by providing a headline, simplifying the information and inserting illustrations, adding information supporting the fact that there is no effect of radiation, as well as information indicating the scale of trouble, and adding information on the effect of radiation within the power plant, on the safety impact of the trouble and on the state of trouble reporting to national and local governments. We also recognized that, to ensure that information is not misleading, we should include specific data on the effect of radiation within the nuclear power station. Moreover, we learned that making the above

  7. Study into the applicabilities of lasers for the dismantling of decommissioned nuclear power plant

    Haferkamp, H.; Bach, F.W.; Vinke, T.; Kinzel, A.; Mack, N.; Kuboschek, M.; Grobe, K.

    1989-01-01

    The project was intended to screen current laser technology for potential applications of laser beams in the dismantling of decommissioned nuclear power plant. As with CO 2 , Nd-YAG, or excimer lasers, developments clearly proceed towards higher output power. The market survey shows the CO 2 -laser to be the most efficient at present, with a great number of laser units available on the market in the range up to 5 kW, and some in the range up to 15 kW. The CO 2 -laser has exclusively been used so far for cutting work in steel plates thicker than 10 mm. Characteristic conditions of application include the high output power of more than 2 kW, long beam lengths, oxygen supply at strongly increased working pressure, sometimes from external sources. The maximum cutting work achieved in the laboratory was 110 mm in structural steel, 90 mm in austenitic steel, and 160 mm in concrete, all under conditions of easy access to the material. It remains to be examined whether steel cutting work at constrained positions will allow separation of wall thicknesses of more than 10 mm. Laser beam cutting under water is feasible in principle but has not been much studied yet. There also are only few sampling results of measurements of dust and aerosol quantities resulting from laser beam cutting work. (orig.) [de

  8. Brighter for small power plants

    Haaland, Leif

    2003-01-01

    The article presents a small tunnel drilling machine aimed at using for the construction of small hydroelectric power plants and mentions briefly some advantages economically and environmentally of both the machine and the power production solution

  9. A study on the ocean circulation and thermal diffusion near a nuclear power plant

    Shu, Kyung Suk; Han, Moon Hee; Kim, Eun Han; Hwang, Won Tae

    1994-08-01

    The thermal discharge used with cooling water at nuclear power plant is released to a neighbour sea and it is influenced on marine environment. The thermal discharge released from power plant is mainly transported and diffused by ocean circulation of neighbour sea. So the evaluation for characteristics of ocean circulation around neighbour sea is firstly performed. The purpose of this research is primarily analyzed the thermal diffusion in sea around Yongkwang nuclear power plant. For this viewpoint, fundamental oceanographic data sets are collected and analyzed in Yellow sea, west sea of Korea, sea around Yongkwang. The ocean circulation and the effects of temperature increase by thermal discharge are evaluated using these data. The characteristics of tide is interpreted by the analysis of observed tidal elevation and tidal currents. The characteristics of temperature and salinity is investigated by the long-term observation of Korea Fisheries Research and Development Agency and the short-term observation around Yongkwang. (Author)

  10. RESERCH STUDIES ON THE LOCATION OF A WAVE ENERGY POWER PLANT WITHIN CONSTANTA AREA

    SAMOILESCU Gheorghe

    2015-05-01

    Full Text Available This paper is based on a research project on the development and installation of the first hydropneumatic plant in the Black Sea. It shows the location and its particularities, existing and previous hydrometeorological conditions, required work, plant qualities and standards to be met. The wave characteristics calculation and the hydrotechnic studies were presented: articulated concrete blocks demolition of the existing breakwater; dredging for the foundation of the plant; accomplish the foundation of the plant; installation of the plant; testing; consolidation and assuring protection of the breakwater; consolidation and assuring protection of the plant. Environmental protection measures are an important part of any research project of this type.

  11. Preliminary study on the analysis of alpha emitters at working places in nuclear power plants

    Kim, Hanna; Kim, Jeong In; Lee, Byoungil [Korea Hydro and Nuclear Power Co., Seoul (Korea, Republic of); Yoon, Suk Won [Korea Institute of Radiological and Medical Sciences National Radiation Emergency Medical Center, Seoul (Korea, Republic of)

    2012-10-15

    Over sea nuclear power plants have been reported cases of internal contamination by alpha nuclides. In many cases, stations encountered significant alpha contamination when aged/legacy equipment was disturbed or handled. Under normal operating conditions, transuranic radionuclides are contained within the fuel rods and therefore are not a contributor to radioactive contamination within a facility. However, transuranic radionuclides result from the presence of tramp-uranium contamination on the exterior of fuel elements. Fuel failures may develop during operating cycles due to a variety of causes, ranging from manufacturing defects to mechanical or abrasive damage. In case of domestic nuclear power plants, the pressure tube replacements in Wolsong Unit 1 and steam generator replacements in Kori Unit 1 were done. Due to deterioration of equipment in accordance with the long-term operation, the domestic nuclear power plants are expected to improve the facilities and the probability of internal exposure from alpha emitters is increasing. The domestic nuclear power plants are only keeping alpha radionuclides of the effluent from the exterior under constant surveillance. The representative areas of CV are just carried out continuous alpha monitoring in during a unit outage. So far, there is no other case with alpha nuclides analysis. As the domestic nuclear power plants are expected to improve the facilities, it is the time to take proactive measures to deal with internal contamination by alpha emitting radioactive elements. In this paper, the possible risk of internal exposure is based on preliminary experiments on the analysis of alpha emitting radioactive elements at working places in nuclear power plants.

  12. Air pollutants conversion study of combustion gas generating by oil fueled thermoelectric power plant to fertilizer byproduct

    Aly, Omar Fernandes

    2001-01-01

    This study concerns the development and application of a SO 2 and NO x simultaneous gas treatment through a 135 MW electron beam flue gas treatment demonstration plant at Piratininga Power Plant located at Sao Paulo, the biggest city in Brazil, around 16 million inhabitants, with serious problems concerning air pollution. This power plant belongs to a service electric utility necessary for the supply of energy to more than 5,800,000 customers, covering an area of 21,168 km 2 where approximately 20,2 million people live. This plant is a 470 MW, 2x100 MW built in 1954 and 2x135 MW erected in 1960, oil fueled (at full load, 2,800 ton per day). The oil is low sulfur content 3 /h for 135 MW generated by the plant. This process aims to reduce SO 2 and NO x gas pollutant emissions attending the Brazilian environmental laws including the expecting future law for NO x levels. The process consists in high energy electron beam irradiation (above 0,8 MeV) of burning gas from the plant at ammonia presence forming as reaction product ammonium sulfate and nitrate that are collecting as dry dust at an electrostatic precipitator. This is economically useful to the plant and to Brazil, a mainly agricultural country. The Feasibility Study for a 135 MW pilot plant installation at Piratininga Power Plant allows the data collection to optimize and to develop this process, the operation and maintenance costs evaluation for the country . After the process implementation, the human resources training aiming the all plant extension of this process and also the technology know how transfer to another industrial process plants like coal fired thermoelectrical power plants, siderurgical , incinerators and chemical industries. (author)

  13. Plant life extension of nuclear power plants. No thank you? A scientific study on the influence of media and communication on the public opinion concerning nuclear power

    Arlt, Dorothee

    2013-01-01

    The present study examined the influence of the individual use of media on attitudes towards nuclear power with focus in the run-time extension of German nuclear power plants, planned by the German government in the year 2010. The theoretical framework for explaining media effects on attitudes based on opinion research as well as on the second-level agenda setting. This approach assumes that highlighting attributes about attitude objects in the media makes them cognitively more accessible for recipients, so that these attributes are used to evaluate attitude object. In this study, arguments for and against the run-time extension were defined as attributes. For the investigation of individual media effects, this study was carried out in a two-method design to combine survey data and content analysis data on an individual level. From 16.08.2010 to 05.09.2010 the data on attitudes towards the planned run-time extension, nuclear power, energy, policy as well as individual media usage was collected in a representative telephone survey of n=551 people in Thuringia. In a quantitative content analysis the pro and contra arguments about the planned run-time extension in n=480 articles and news items, published during six months before the political decision, were analyzed. The findings of the content analysis showed that the media reported from 08.03.2010 to 05.09.2010 overall positively about the planned run-time extension and that the coverage intensity increased significantly shortly before the political decision. The main focus was on arguments regarding the efficiency and security of supply. By combining the content analysis data with the media usage data, new variables (sum and average value indices) for the specific individual media input of arguments about the run-time extension were formed. With these variables medium- and long-term media effects on attitudes towards nuclear power were tested. The results of the regression analyses showed that the individual media

  14. Summary of nuclear power plant construction

    Tamura, Saburo

    1973-01-01

    Various conditions for the construction of nuclear power plants in Japan without natural resources were investigated. Expansion of the sites of plants, change of reactor vessels, standardization of nuclear power plants, possiblity of the reduction of construction period, approaching of nuclear power plants to consuming cities, and group construction were studied. Evaluation points were safety and economy. Previous sites of nuclear power plants were mostly on plane ground or cut and enlarge sites. Proposals for underground or offshore plants have been made. The underground plants were made at several places in Europe, and the ocean plant is now approved in U.S.A. as a plant on a man-made island. Vessels for containing nuclear reactors are the last barriers to the leakage of radioactive substance. At the initial period, the vessels were made of steel, which were surrounded by shielding material. Those were dry well type containers. Then, vessel type changed to pressure-suppression type wet containers. Now, it tends to concrete (PC or RC) type containers. There is the policy on the standardization of nuclear power plants by U.S.A.E.C. in recent remarkable activity. The merit and effect of the standardization were studied, and are presented in this paper. Cost of the construction of nuclear power plants is expensive, and interest of money is large. Then, the reduction of construction period is an important problem. The situations of plants approaching to consuming cities in various countries were studied. Idea of group construction is described. (Kato, T.)

  15. Are atomic power plants saver than nuclear power plants

    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

  16. Employing modern power plant simulators in nuclear power plants

    Niedorf, V.; Storm, J.

    2005-01-01

    At the present state of the art, modern power plant simulators are characterized by new qualitative features, thus enabling operators to use them far beyond the traditional field of training. In its first part, this contribution presents an overview of the requirements to be met by simulators for multivalent uses. In part two, a survey of the uses and perspectives of simulation technology in power plants is presented on the basis of experience accumulated by Rheinmetall Defence Electronics (RDE).Modern simulators are shown to have applications by far exceeding traditional training areas. Modular client - sever systems on standard computers allow inexpensive uses to be designed at several levels, thus minimizing maintenance cost. Complex development and running time environments, like the SEMS developed by RDE, have made power plant simulators the workhorses of power plant engineers in all power plant areas. (orig.)

  17. A Study on the Approach to Quality Management in Construction of Nuclear Power Plants

    Pingish, Panupong [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Choi, Kwang Sik [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2010-05-15

    The quality of works and services in nuclear facilities are important aspect of public safety and environmental protection. In the general legal framework for the regulation of nuclear power plants of each country, the requirement which effectiveness, overall quality management programme be established should be present. The organization having overall responsibility for a nuclear power plant shall be responsible for the establishment and implementation of the overall quality management programme for that plant. The construction methods available for new nuclear power plants are generally the same as those used for other big construction projects. The construction stage of a nuclear power plant includes a multitude of activities affecting quality which are performed by various organizations with specific responsibilities assigned to them. At the present, the IAEA source materials have been changing some documents for supporting tendency in the nuclear technology likewise in term of quality assurance concept to quality management concept. The principle goal for quality management is achieved assurance and sustainable with nuclear safety. This system brings all the requirements for managing facilities and activities together by only one system

  18. A Study on the Approach to Quality Management in Construction of Nuclear Power Plants

    Pingish, Panupong; Choi, Kwang Sik

    2010-01-01

    The quality of works and services in nuclear facilities are important aspect of public safety and environmental protection. In the general legal framework for the regulation of nuclear power plants of each country, the requirement which effectiveness, overall quality management programme be established should be present. The organization having overall responsibility for a nuclear power plant shall be responsible for the establishment and implementation of the overall quality management programme for that plant. The construction methods available for new nuclear power plants are generally the same as those used for other big construction projects. The construction stage of a nuclear power plant includes a multitude of activities affecting quality which are performed by various organizations with specific responsibilities assigned to them. At the present, the IAEA source materials have been changing some documents for supporting tendency in the nuclear technology likewise in term of quality assurance concept to quality management concept. The principle goal for quality management is achieved assurance and sustainable with nuclear safety. This system brings all the requirements for managing facilities and activities together by only one system

  19. Steam explosions-induced containment failure studies for Swiss nuclear power plants

    Zuchuat, O.; Schmocker, U. [Swiss Federal Nuclear Safety Inspectorate, Villigen (Switzerland); Esmaili, H.; Khatib-Rahbar, M.

    1998-01-01

    The assessment of the consequences of both in-vessel and ex-vessel energetic fuel-coolant interaction for Beznau (a Westinghouse pressurized water reactor with a large, dry containment), Goesgen (a Siemens/KWU pressurized water reactor with a large, dry containment) and Leibstadt (a General Electric boiling water reactor-6 with a free standing steel, MARK-III containment) nuclear power plants is presented in this paper. The Conditional Containment Failure Probability of the steel containment of these Swiss nuclear power plants is determined based on different probabilistic approaches. (author)

  20. Staffing decision processes and issues: Case studies of seven US Nuclear Power Plants

    Melber, B.; Roussel, A.; Baker, K.; Durbin, N.; Hunt, P.; Hauth, J.; Forslund, C.; Terrill, E.; Gore, B.

    1994-03-01

    The objective of this report is to identify how decisions are made regarding staffing levels and positions for a sample of U.S. nuclear power plants. In this report, a framework is provided for understanding the major forces driving staffing and the implications of staffing decisions for plant safety. The focus of this report is on driving forces that have led to changes in staffing levels and to the establishment of new positions between the mid-1980s and the early 1990s. Processes used at utilities and nuclear power plants to make and implement these staffing decisions are also discussed in the report. While general trends affecting the plant as a whole are presented, the major emphasis of this report is on staffing changes and practices in the operations department, including the operations shift crew. The findings in this report are based on interviews conducted at seven nuclear power plants and their parent utilities. A discussion of the key findings is followed by a summary of the implications of staffing issues for plant safety

  1. The Feasibility study of laser peening effects on the Nuclear power plants Using Shot peening treatment with operating temperature

    Kim, Jong Cheon; Kim, Tae Hyung; Cheong, S. K.; Cho, Hong Seok

    2010-01-01

    Recently, the nuclear power plants industry was faced with material aging problems. One of them is Primary water stress corrosion cracking (PWSCC). Even if Alloy 600, which is a nickel based superalloy, has been used in some parts of nuclear power plants, it is widely used in the manufacturing of commercial and military components. The Alloy 600 is a standard structural engineering material which requires the resistance to corrosion and thermal effects. However, some parts of BMI nozzle have PWSCC problem. Several methods have been used to prevent PWSSC. Typically, peening process is used extensively in the industry to improve life time and to mitigate stress corrosion cracking (SCC). Laser peening (LP) is one of the best ways to achieve the above reasons. This technology was already applied to nuclear power plants by developed countries. Nowadays Korea nuclear power plants industry is highly ranked in the world market. Thus, the demands of laser peening technology will increase. However, it is very difficult to characterize the material properties after peening treatment on the parts of nuclear power plants. Therefore, we accomplished a precedent study of experiments to investigate the effects of peening process on the Alloy 600, and the threshold temperature for stress relief and the effect of LP through the Shop peening(SP). LP and SP process have equal mechanism but just different peening media. In this paper, to determine the effects of laser peening process on the nuclear power plants manufacture Alloy 600 using the shot peening treatment with operating temperatures

  2. Radioecological studies of activation products released from a nuclear power plant into the marine environment

    Nilsson, M.; Mattsson, S.; Holm, E.

    1984-01-01

    The Barseback nuclear power plant, located on the Oresund sound between Denmark and Sweden, consists of two boiling water reactors. The release of radionuclides, mainly activation products, is quite low during normal operation. During the summer, when annual overhaul and partial refuelling take place, the discharge is much higher. Samples of seaweeds and crustaceans collected along the coast were analyzed for radionuclides. Seaweeds (Fucus vesiculosus, F. Serratus, Ascophyllum nodosum and Cladophora glomerata) and crustaceans (Idothea and Gammarus) proved to be excellent bioindicators for radioactive corrosion products released from the nuclear power plant into the marine environment. These bioindicators have been used to map the spatial and temporal distribution of the released radioactivity. The activity has been followed up to 150 km from the power plant, and the decrease in activity concentration in the bioindicators with distance can be expressed by a power function. The variation with time of activity concentration reflects the amount of activity discharged from the power plant, with good resolution in time. The bioindicators exhibit different uptake patterns of the radionuclides detected. The crustacean Idothea showed variations in the Co/sup 60/ activity concentration between winter and summer. 9 references, 12 figures, 2 tables.

  3. Study on modular technology based on the reference nuclear power plant

    Lu Qinwu; Zhao Shuyu; Li Yi; Han Xiaoping; Chai Weidong; Zhang Shuxia

    2014-01-01

    As an important technology for shortening the construction period and reducing the cost of nuclear power project, modular technology has become one of the development orientations of the third generation nuclear power plant. Taking CPR1000 nuclear power reactor as reference plant and drawing on advanced foreign technology of modularization, the overall concept design has been completed with the help of the self-developed 3D modular design system. On this basis, a typical detailed design work has been carried out so as to verify the feasibility of technology. Besides, an analysis on implementation of modular technology has been made from two aspects (procurement and construction), and the feasibility of research results in actual project has been evaluated. It provides references for the promotion of self-reliant modular technology in nuclear power project in China. (authors)

  4. A Study on Human Factors in Maintenance of a Nuclear Power Plant (NPP)

    Park, Young Ho; Seong, Poong Hyun

    2006-01-01

    In human factors research, more attention has been devoted to the operation of a nuclear power plant (NPP) than to their maintenance. However, more NPP incidents are caused by inadequate maintenance rather than by faulty operation. There is a trend in NPP toward introducing digital technology into safety and non-safety systems. This lead to changes of maintenance, and support systems such as diagnosis system, augmentation system and handy terminal will be developed. In this context, it is important to identify tasks of human related to each phase of maintenance and their relation in order to apply those to maintenance. However, there are few researches of human factors in maintenance. This paper studies on framework of cognitive task analysis for developing maintenance support systems

  5. Study on advanced nuclear power plants expert evaluation system in China

    Zhang Qi; Yoshikawa, Hidekazu; Shimoda, Hiroshi; Zhou Zhiwei; Zhu Shutang; Ren Junsheng; Yang Mengjia; Gu Junyang

    2005-01-01

    Based on current status and developing trend of nuclear power plant technology, an evaluation software system is developed to assess advanced NPPs systematically according to a set of pre-established evaluation indices. The selection and classification of the indices, the determination of their weighting factors in applying AHP (analytic hierarchy process) method are discussed. The Fuzzy Comprehensive method and the Fuzzy Borda Number method are studied in detail. The original input data required by the evaluation system are deduced from the expert survey sheets Evaluation results with common significance of public attraction are discussed and analyzed according to the opinions of different experts grouped by age, profession and working expertise etc. The evaluation system is computer network based with high flexible and user friendly human-machine interface on which it is easy to manipulate and update the evaluation system, and to display evaluation results as well. (author)

  6. A Study on a Hybrid Approach for Diagnosing Faults in Nuclear Power Plant

    Yang, M.; Zhang, Z.J.; Peng, M.J.; Yan, S.Y.; Wang, H.; Ouyang, J.

    2006-01-01

    Proper and rapid identification of malfunctions is of premier importance for the safe operation of Nuclear Power Plants (NPP). Many monitoring or/and diagnosis methodologies based on artificial and computational intelligence have been proposed to aid operator to understand system problems, perform trouble-shooting action and reduce human error under serious pressure. However, because no single method is adequate to handle all requirements for diagnostic system, hybrid approaches where different methods work in conjunction to solve parts of the problem interest researchers greatly. In this study, Multilevel Flow Models (MFM) and Artificial Neural Network (ANN) are proposed and employed to develop a fault diagnosis system with the intention of improving the success rate of recognition on the one hand, and improving the understandability of diagnostic process and results on the other hand. Several simulation cases were conducted for evaluating the performance of the proposed diagnosis system. The simulation results validated the effectiveness of the proposed hybrid approach. (authors)

  7. Socioeconomic impacts of nuclear power plant siting: a case study of two New England communities

    Purdy, B.J.

    1976-01-01

    An examination is presented of the social, economic and political/institutional impacts of two operating nuclear power complexes on two New England communities. The work is one of a series planned to broaden knowledge of the effects of large energy-generating facilities upon the social structure of local communities. Its primary objectives are to investigate and assess social and economic impacts resulting from construction and operation of nuclear power plants and to generate hypotheses about such impacts for future testing

  8. Studying heat integration options for steam-gas power plants retrofitted with CO2 post-combustion capture

    Carapellucci, Roberto; Giordano, Lorena; Vaccarelli, Maura

    2015-01-01

    Electricity generation from fossil fuels has become a focal point of energy and climate change policies due to its central role in modern economics and its leading contribution to greenhouse gas emissions. Carbon capture and sequestration (CCS) is regarded by the International Energy Agency as an essential part of the technology portfolio for carbon mitigation, as it can significantly reduce CO 2 emissions while ensuring electricity generation from fossil fuel power plants. This paper studies the retrofit of natural gas combined cycles (NGCCs) with an amine-based post-combustion carbon capture system. NGCCs with differently rated capacities were analysed under the assumptions that the heat requirement of the capture system was provided via a steam extraction upstream of the low-pressure steam turbine or by an auxiliary unit that was able to reduce the power plant derating related to the energy needs of the CCS system. Different types of auxiliary units were investigated based on power plant size, including a gas turbine cogeneration plant and a supplementary firing unit or boiler fed by natural gas or biomass. Energy and economic analyses were performed in order to evaluate the impact of type and layout of retrofit option on energy, environmental and economic performance of NGCCs with the CCS system. - Highlights: • Steam-gas power plants with an amine-based CO 2 capture unit are examined. • The study concerns three combined cycles with different capacity and plant layout. • Several options to fulfil the heat requirement of the CCS system are explored. • Steam extraction significantly reduces the capacity of steam-gas power plant. • An auxiliary combined heat and power unit allows to reduce power plant derating

  9. Nuclear power plant

    Urata, Hidehiro; Oya, Takashi

    1996-11-05

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  10. Nuclear power plant

    Urata, Hidehiro; Oya, Takashi.

    1996-01-01

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  11. Pipelines in power plants

    Oude-Hengel, H.H.

    1978-01-01

    Since the end of the Sixties, steam-transporting pipelines are given great attention, as pipeline components often fail, partially even long before their designed operation time is over. Thus, experts must increasingly deal with questions of pipelines and their components. Design and calculation, production and operation of pipelines are included in the discussion. Within the frame of this discussion, planners, producers, operators, and technical surveillance personnel must be able to offer a homogenous 'plan for assuring the quality of pipelines' in fossil and nuclear power plants. This book tries to make a contribution to this topic. 'Quality assuring' means efforts made for meeting the demands of quality (reliability). The book does not intend to complete with well-known manuals, as for as a complete covering of the topic is concerned. A substantial part of its sections serves to show how quality assurance of pipelines can be at least partially obtained by surveillance measures beginning with the planning, covering the production, and finally accompanying the operation. There is hardly need to mention that the sort of planning, production, and operation has an important influence on the quality. This is why another part of the sections contain process aspects from the view of the planners, producers, and operators. (orig.) [de

  12. Nuclear power plants

    Kiyokawa, Teruyuki; Soman, Yoshindo.

    1985-01-01

    Purpose: To constitute a heat exchanger as one unit by integrating primary and secondary coolant circuits with secondary coolant circuit and steam circuit into a single primary circuit and steam circuit. Constitution: A nuclear power plant comprises a nuclear reactor vessel, primary coolant pipeways and a leakage detection system, in which a dual-pipe type heat exchanger is connected to the primary circuit pipeway. The heat conduction tube of the heat exchanger has a dual pipe structure, in which the inside of the inner tube is connected to the primary circuit pipeway, the outside of the outer tube is connected to steam circuit pipeway and a fluid channel is disposed between the inner and outer tubes and the fluid channel is connected to the inside of an expansion tank for intermediate heat medium. The leak detection system is disposed to the intermediate heat medium expansion tank. Sodium as the intermediate heat medium is introduced from the intermediate portion (between the inner and outer tubes) by way of inermediate heat medium pipeways to the intermediate heat medium expansion tank and, further, to the intermediate portion for recycling. (Kawakami, Y.)

  13. Underground nuclear power plant

    Takahashi, Hideo.

    1997-01-01

    In an underground-type nuclear power plant, groups of containing cavities comprising a plurality of containing cavities connected in series laterally by way of partition walls are disposed in parallel underground. Controlled communication tunnels for communicating the containing cavities belonging to a control region to each other, and non-controlled communication tunnels for communicating containing cavities belonging to a non-controlled area to each other are disposed underground. A controlled corridor tunnel and a non-controlled corridor tunnel extended so as to surround the containing cavity groups are disposed underground, and the containing cavities belonging to the controlled area are connected to the controlled corridor tunnel respectively, and the containing cavities belonging to the non-controlled area are connected to the non-controlled corridor tunnel respectively. The excavating amount of earth and sand upon construction can be reduced by disposing the containing cavity groups comprising a plurality of containing cavities connected in series laterally. The time and the cost for the construction can be reduced, and various excellent effects can be provided. (N.H.)

  14. Methodology for Scaling Fusion Power Plant Availability

    Waganer, Lester M.

    2011-01-01

    Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, 'Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the 'teething' problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated 'mature' subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.

  15. Ocean power plants

    Mazurkiedicz, B.; Sliwa, B.

    1982-01-01

    Plans are examined for OTES of close and open cycles. Examples of design of TO are presented. Main design elements of the OTES are indicated and their arrangement. The OTES can be realized even now with comparatively small capital investments. Searches are made for solutions which would make it possible to construct the OTES and not in tropical regions, i.e., with very small temperature differences. The studies indicated that with a difference of temperatures 4.5/sup 0/C and temperature of the thermal water 5.5/sup 0/C, it is possible to build OTES with power 100 MW. With difference in temperature 5/sup 0/C, the power will reach 130 MW.

  16. Comparative analysis of the conceptual design studies of potential early commercial MHD power plants (CSPEC)

    Sovie, R. J.; Winter, J. M.; Juhasz, A. J.; Berg, R. D.

    A conceptual design study of the MHD/steam plant that incorporates the use of oxygen enriched air preheated in a metallic heat exchanger as the combustor oxidant showed that this plant is the most attractive for early commercial applications. The variation of performance and cost was investigated as a function of plant size. The contractors' results for the overall efficiencies are in reasonable agreement considering the slight differences in their plant designs. NASA LeRC is reviewing cost and performance results for consistency with those of previous studies, including studies of conventional steam plants. LeRC in house efforts show that there are still many tradeoffs to be considered for these oxygen enriched plants and considerable variations can be made in channel length and level of oxygen enrichment with little change in overall plant efficiency.

  17. Power plants and safety 1982

    1982-01-01

    The papers of this volume deal with the whole range of safety issues from planning and construction to the operation of power plants, and discuss also issues like availability and safety of power plants, protective clothes and their incommodating effect, alternatives for rendering hot-water generators safe and the safety philosophy in steam turbine engineering. (HAG) [de

  18. Thermodynamic optimization of power plants

    Haseli, Y.

    2011-01-01

    Thermodynamic Optimization of Power Plants aims to establish and illustrate comparative multi-criteria optimization of various models and configurations of power plants. It intends to show what optimization objectives one may define on the basis of the thermodynamic laws, and how they can be applied

  19. Owners of nuclear power plants

    Wood, R.S.

    1991-07-01

    This report indicates percentage ownership of commercial nuclear power plants by utility companies. The report includes all plants operating, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review, but does not include those plants announced but not yet under review or those plants formally cancelled. Part 1 of the report lists plants alphabetically with their associated applicants or licensees and percentage ownership. Part 2 lists applicants or licensees alphabetically with their associated plants and percentage ownership. Part 1 also indicates which plants have received operating licenses (OLS)

  20. Study on condition monitoring techniques for low voltage electrical cables in nuclear power plants

    Hirao, Hideo; Sakai, Takeshi; Kajimura, Yuusaku

    2017-01-01

    Low voltage electrical cables installed in nuclear power plants are required to maintain its function in a design basis accident environment and they are qualified to that environment. The cables degrade also in normal operating conditions due to ageing and they must maintain integrity until the end of their qualified life. Demands for the condition monitoring technique for low voltage electrical cables have therefore been increasing as nuclear power plants operate longer. A single perfect method for this purpose is not available yet, but the possibility to use two different types of methods which can complement with each other has been examined. The combination of Fourier Transform Infrared Spectroscopy (FT-IR) and Indenter Modulus (IM) method was found highly effective. FT-IR is a method that determines chemical properties (changes in molecular bindings) of cables by using infrared rays, while IM is a method that determines mechanical properties (changes in hardness) of cables by indenters. Both methods are non-destructive and can be applied in-situ to the same material. Reliability of the evaluation can be assured by applying two different types of measurement principles that complement with each other. In this study, various cable samples with different kinds of insulation material (cross-linked polyethylene, ethylene propylene rubber, silicone rubber etc.) were aged with a special accelerated ageing technique which applies simultaneous thermal and radiation ageing to simulate ageing phenomena in a more realistic manner, and the degree of ageing was evaluated with FT-IR and IM. The evaluation result shows good correlation with ageing time and other ageing properties for most material types and the effectiveness of these methods were demonstrated. (author)

  1. Birth Outcomes after the Fukushima Daiichi Nuclear Power Plant Disaster: A Long-Term Retrospective Study

    Claire Leppold

    2017-05-01

    Full Text Available Changes in population birth outcomes, including increases in low birthweight or preterm births, have been documented after natural and manmade disasters. However, information is limited following the 2011 Fukushima Daiichi Nuclear Power Plant Disaster. In this study, we assessed whether there were long-term changes in birth outcomes post-disaster, compared to pre-disaster data, and whether residential area and food purchasing patterns, as proxy measurements of evacuation and radiation-related anxiety, were associated with post-disaster birth outcomes. Maternal and perinatal data were retrospectively collected for all live singleton births at a public hospital, located 23 km from the power plant, from 2008 to 2015. Proportions of low birthweight (<2500 g at birth and preterm births (<37 weeks gestation at birth were compared pre- and post-disaster, and regression models were conducted to assess for associations between these outcomes and evacuation and food avoidance. A total of 1101 live singleton births were included. There were no increased proportions of low birthweight or preterm births in any year after the disaster (merged post-disaster risk ratio of low birthweight birth: 0.98, 95% confidence interval (CI: 0.64–1.51; and preterm birth: 0.68, 95% CI: 0.38–1.21. No significant associations between birth outcomes and residential area or food purchasing patterns were identified, after adjustment for covariates. In conclusion, no changes in birth outcomes were found in this institution-based investigation after the Fukushima disaster. Further research is needed on the pathways that may exacerbate or reduce disaster effects on maternal and perinatal health.

  2. Feasibility study of a Green Power Plant. Final report. [Offshore pumped hydro storage

    NONE

    2013-03-15

    This project is a technical evaluation and a feasibility study of a concept called the Green Power Plant (GPP), developed by Seahorn Energy Aps. The Green Power Plant is an offshore pumped hydro storage facility constructed from prefabricated elements and with integrated renewable energy production. Pumped hydro storage is a known technology with a proven roundtrip energy storage efficiency of 80%. The focus of the GPP project is on simplifying and industrializing the construction of the reservoir wall, thereby achieving a cost efficient solution. The reservoir structure is dependent on the site on which the reservoir is established, thus Kriegers Flak in the Baltic Sea has been chosen as basis for the technical evaluation. As soil conditions vary, the technical evaluations have been based on a general soil profile. A water depth of 25m has been chosen as basis for the evaluation. A reservoir with a diameter of 2 km has been evaluated as baseline scenario. Feasibility of the GPP was evaluated based on the cost and income estimates. For the baseline scenario an internal rate of return of 6.6% was found for a period of 35 years. A sensitivity analysis reveals internal rates of return over 35 years varying from 4.9% to 10.9%. Especially larger reservoir diameters increase profitability of the GPP. The results from this project will be utilized in raising funds for further development of the GPP concept. Seahorn Energy Aps aims at optimizing the wind turbine integration, the steel pile wall structure and the pump-turbine integration in a future project towards construction of a demonstration facility. (LN)

  3. Thermal-hydraulic studies on the safety of VVER-440 type nuclear power plants

    Tuunanen, J.

    1994-01-01

    The thesis includes several thermal-hydraulic analyses related to the Loviisa VVER-440 nuclear power plant units. The work consists of experimental studies, analysis of the experiments, analysis of some plant transients and development of a calculational model for calculation of boric concentrations in the reactor. In the first part of thesis, in the case of simulation of boric acid solution behaviour during long-term cooling period of LOCAs, experiments were performed in scaled-down test facilities. The experimental data together with the results of RELAP5/MOD3 simulations were used to develop a model for calculations of boric acid concentrations in the reactor during LOCAs. In the second part, in the case of simulation of horizontal generators, experiments were performed with PACTEL integral test loop to simulate loss of feedwater transients. The PACTEL experiments as well as earlier REWETT-III natural circulation tests, were analyzed with RELAP5/MOD3 Version 5m5 code. The third part of the work consists of simulations of Loviisa VVER reactor pump trip transients with RELAP5/MOD1-Eur, RELAP5/MOD3 and CATHARE codes. (56 refs., 9 figs.)

  4. Fire Risk Scoping Study: Investigation of nuclear power plant fire risk, including previously unaddressed issues

    Lambright, J.A.; Nowlen, S.P.; Nicolette, V.F.; Bohn, M.P.

    1989-01-01

    An investigation of nuclear power plant fire risk issues raised as a result of the USNRC sponsored Fire Protection Research Program at Sandia National Laboratories has been performed. The specific objectives of this study were (1) to review and requantify fire risk scenarios from four fire probabilistic risk assessments (PRAs) in light of updated data bases made available as a result of USNRC sponsored Fire Protection Research Program and updated computer fire modeling capabilities, (2) to identify potentially significant fire risk issues that have not been previously addressed in a fire risk context and to quantify the potential impact of those identified fire risk issues where possible, and (3) to review current fire regulations and plant implementation practices for relevance to the identified unaddressed fire risk issues. In performance of the fire risk scenario requantifications several important insights were gained. It was found that utilization of a more extensive operational experience base resulted in both fire occurrence frequencies and fire duration times (i.e., time required for fire suppression) increasing significantly over those assumed in the original works. Additionally, some thermal damage threshold limits assumed in the original works were identified as being nonconservative based on more recent experimental data. Finally, application of the COMPBRN III fire growth model resulted in calculation of considerably longer fire damage times than those calculated in the original works using COMPBRN I. 14 refs., 2 figs., 16 tabs

  5. Study of the influencies of Angra-1 nuclear power plant construction in Angra dos Reis

    Ferreira Netto, L.

    1982-01-01

    The report presents a comprehensive evaluation of the influence caused by Angra-1 Nuclear Power Plants (Central Nuclear Almirante Alvaro Alberto) construction on the Angra dos Reis City - Rio de Janeiro - Brazil. The analysis performed adopts a multi-dimensional methodology with four analysis dimensions: political-institutional, physical-territorial, social-economic and temporal. (author)

  6. Study of operating procedures in nuclear power plants: Practices and problems

    Morgenstern, M.H.; Barnes, V.E.; McGuire, M.V.; Radford, L.R.; Wheeler, W.A.

    1987-02-01

    This report describes the project activities, findings, and recommendations of a project entitled ''Program Plan for Assessing and Upgrading Operating Procedures for Nuclear Power Plants.'' The project was performed by the Pacific Northwest Laboratory and Battelle Human Affairs Research Centers for the Division of Human Factors Technology, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission (NRC). The project team analyzed and evaluated samples of normal and abnormal operating procedures from 31 commercial nuclear power plant sites operating in the United States. The project team also visited nine nuclear power plants in the United States to obtain information on the development, use, and control of operating procedures. A peer review group was convened to advise the project team on the conduct of the project and to review and comment on the project report. The report contains findings on the usability of operating procedures and on practices concerning the development, use, an control of operating procedures in nuclear power plants. The report includes recommendations to the NRC on the need to upgrade the quality of operating procedures. The report also discusses an approach to a program plan to assess and upgrade operating procedures

  7. Study of arcview GIS application in the nuclear power plant emergency response decision support system

    Li Peng; Chen Lin; Dong Binjiang

    2003-01-01

    It is very significant to apply the technique of GIS to the development of the Nuclear Power Plant Emergency Response Decision Support System. On the basis of the software system ArcView. This paper investigate the framework, the function and the development methods of the system. (authors)

  8. Study on the distribution coefficient during environmental impact evaluation in Chinese inland nuclear power plants

    Xu Haifeng; Shang Zhaorong; Chen Fangqiang

    2012-01-01

    Description the radionuclide distribution coefficient of the important factors in the river sediment systems, at home and abroad the main method of measuring the K d value and progress in China's inland nuclear power plant environmental impact assessment of workers to carry out the distribution coefficient K d value measurement ideas put forward recommendations. (authors)

  9. Study the dispersion the possible thermal discharges to Juragua nuclear power plant. Preliminary results

    Munnoz Caravaca, A.; Artega Rodriguez, H.; Diaz Asencio, M.; Cartas Aguila, H.

    1998-01-01

    The present work has as objective to present the results the evaluation to the surface area impact to the waters cooling discharges the Juragua nuclear power plant, by means of hydrodynamic models that described the possible distribution the same ones in the boundary marine means to the location

  10. Nuclear power plant diagnostic system

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  11. A study of a small nuclear power plant system for district heating

    Imamura, Mitsuru; Sato, Kotaro; Narabayashi, Tadashi; Shimazu, Yoichiro; Tsuji, Masashi

    2009-01-01

    We have studied nuclear power plant for district heating. Already some towns and villages in Hokkaido have requested small reactor for district heating. Using existing technology allows us to shorten development period and to keep a lid on development cost. We decided to develop new reactor based on 'MUTSU' reactor technology because 'MUTSU' had already proved its safety. And this reactor was boron free reactor. It allows plant system to reduce the chemical control system. And moderator temperature coefficient is deeply negative. It means to improve its operability and leads to dependability enhancement. We calculated burn-up calculation of erbium addition fuel. In the result, the core life became about 10 years. And we adapt the cassette type refueling during outagein in order to maintain nonproliferation. In the district heating system, a double heat exchanger system enables to response to load change in season. To obtain the acceptance of public, this system has a leak prevention system of radioactive materials to public. And road heating system of low grade heat utilization from turbine condenser leads to improve the heat utilization efficiency. We carried out performance evaluation test of district heating pipeline. Then the heat loss of pipeline is estimated at about 0.440degC/km. This result meets general condition, which is about 1degC/km. This small plant has passive safety system. It is natural cooling of containment vessel. In case of loss of coolant accident, decay heat can remove by natural convection air cooling after 6 hours. Decay heat within 6 hours can remove by evaporative heat transfer of pool on containment vessel. (author)

  12. VGB Congress 'Power Plants 2006'

    Anon.

    2006-01-01

    The VGB Congress 'Power Plants' took place in Dresden, 27 th to 29 th September 2006 under the auspices of the Federal Minister for Economics and Technology, Michael Glos. The motto of this year's Congress was 'Future becomes Reality - Investments in New Power Plants'. More than 1,200 participants from Germany and abroad attended the plenary and technical lectures on the topics 'Market and Competition' as well as 'Technology, Operation and Environment' for information and discussion. Special papers were dealing with further issues like 'Generation Market in Europe', 'Clean Power Technology Platform', French policy for new power plants as well as potentials and technology of renewables. (orig.)

  13. Nuclear power plant V-1

    1998-01-01

    The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

  14. A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

    Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2010-05-15

    Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

  15. A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

    Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon; Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub

    2010-01-01

    Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

  16. Preliminary study on acceptability of scope of thermal discharge mixing zone for nuclear power plant

    Liu Yongye; Yang Yang; Wang Liang; Chen Xiaoqiu; Liu Senlin

    2012-01-01

    Based on the situation that the existing domestic temperature control standards are not performable, the preliminary study on the acceptability of the mixing zone scope of thermal discharge for nuclear power plant was conducted in this paper, taking a coastal power station SNP as a case. The following preliminary conclusions could be drawn from the results of cluster analysis of the SNP site under different results of mathematical modeling and physical model test: 1) The influence intensity of ecological function of the SNP site seawater is small and the scope of thermal discharge mixing zone is acceptable under SNP-1 (Unit 1 and 2) operating condition; 2) the influence intensity of ecological function of the SNP site seawater is small and the scope of thermal discharge mixing zone is acceptable in spring under SNP-1 (Unit 1 and 2) and SNP-2 (Unit 3 and 4) operating condition, while the influence intensity of ecological function of the SNP site seawater is large and the scope of mixing zone is unacceptable in autumn under the same operating condition. (authors)

  17. Experimental study of the combined utilization of nuclear power heating plants for big towns and industrial complexes

    Neumann, J.; Barabas, K.

    1977-01-01

    The paper describes a comparison of nuclear power heating plants with an output corresponding to 1000MW(e) with plants of the same output using coal or oil. The economic aspects are compared, both as regards investment and operation costs. The comparison of the environmental aspects is performed on the atmospheric pollution from exhausts and gaseous emission and on the thermal pollutions in hydrosphere and atmosphere. Basic nuclear power plant schemes with two PWRs, each of 1500MW(th), are described. The plant supplies electric power and heat for factories and municipal heating systems (apartments, shops, and other auxiliary municipal facilities). At the same time the basic heat-flow diagram of a nuclear power heating plant is given, together with the relative losses. The study emphasizes the possible utilization of waste heat for heating glasshouses of 200m 2 . The problems of utilizing waste heat, and the needs of a big town and of industrial complexes in the vicinity of the nuclear power heating plant are also considered. (author)

  18. Emergency power systems at nuclear power plants

    1982-01-01

    This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

  19. A study on the crack inspection signal characteristics for power plant components by phased array UT

    Cho, Yong Sang; Lim, Sang Gyu; Kil, Du Song

    2001-01-01

    Phased array ultrasonic testing system has become available for practical application in complicated geometry such as turbine blade root, tenon, disc in power industry. This research describes the characteristics of phased array UT signal for various type of blade roots in thermal Power Plant turbines. This application of Phased array ultrasonic testing system has been promoted mainly to save inspection time and labor cost of turbine inspection. The characteristic of phase array UT signal for power plant component is very simple to understand but to difficult for perform the inspection. Since our sophisticated inspection technique and systems are essential for the inspection of steam turbine blade roots that require high reliability, we intend to develop new technology and improve phased array technique based on the wide and much experience for the inspection of turbine components.

  20. Study of Real Time Location System For Worker in Containment Building at Nuclear Power Plant

    Lee, S. Y.; Kim, G. S. [Samchang Enterprise Company, Ulsan (Korea, Republic of); Kim, H. S. [Ulsan Univ., Ulsan (Korea, Republic of)

    2012-03-15

    Workers are required special management to minimize radiation exposure in nuclear power plant. Especially, there are many limitation in their activities at containment building in nuclear power plant. Test personnel shall administer the workers by tracing the location of them inside containment building in nuclear power plant. They may be exposed to the unnecessary radiation due to a complex and high radiation area in the building. Test personnel needs to manage efficiently for worker's safety and work hours at containment building. Therefore, it is critical for the test personnel to notice the risk to the workers by identifying the location when the workers are facing the dangerous situation on the high area. In this paper, we introduce requirements and design method to develop the one and two dimensional RTLS(Real Time Locating System) by using CSS(Chirp Spread Spectrum) which enables precise location measurement and robust data communication even indoor environment with serious electromagnetic interference caused by complicated structure such as the inside of containment building in the nuclear power plant. In the algorithm to compute the distance, it is suggested to use SDS-TWR(Symmetrical Double-Sided Two-Way Ranging) to solve the issue of indirect routes, and develop the power circuit with 10mW of designing gain for output power to meet the KCC standard in order to increase the raging distance, in addition, communication between Anchor and distance measuring computer shall be designed to increase energy using time of Tags(nodes) by using CAN(Controller Area Network) communication.

  1. Accidents with nuclear power plants, ch. 11

    Anon.

    1976-01-01

    A recalculation of the consequences of nuclear power plant accidents is presented taking into account different parameters or different quantities than those usually accepted. A case study of a nuclear power plant planned for the Eems-river estuary in the Netherlands is presented

  2. Evaluation of uncertainties in benefit-cost studies of electrical power plants. II. Development and application of a procedure for quantifying environmental uncertainties of a nuclear power plant. Final report

    Sullivan, W.G.

    1977-07-01

    Steam-electric generation plants are evaluated on a benefit-cost basis. Non-economic factors in the development and application of a procedure for quantifying environmental uncertainties of a nuclear power plant are discussed. By comparing monetary costs of a particular power plant assessed in Part 1 with non-monetary values arrived at in Part 2 and using an evaluation procedure developed in this study, a proposed power plant can be selected as a preferred alternative. This procedure enables policymakers to identify the incremental advantages and disadvantages of different power plants in view of their geographic locations. The report presents the evaluation procedure on a task by task basis and shows how it can be applied to a particular power plant. Because of the lack of objective data, it draws heavily on subjectively-derived inputs of individuals who are knowledgeable about the plant being investigated. An abbreviated study at another power plant demonstrated the transferability of the general evaluation procedure. Included in the appendices are techniques for developing scoring functions and a user's manual for the Fortran IV Program

  3. Overview of the ARIES-RS reversed-shear tokamak power plant study

    Najmabadi, F.; Billone, M.C.

    1997-01-01

    The ARIES-RS tokamak is a conceptual, D-T-burning 1000 MWe power plant. As with earlier ARIES design studies, the final design of ARIES-RS was obtained in a self-consistent manner using the best available physics and engineering models. Detailed analyses of individual systems together with system interfaces and interactions were incorporated into the ARIES systems code in order to assure self-consistency and to optimize towards the lowest cost system. The ARIES-RS design operates with a reversed-shear plasma and employs a moderate aspect ratio (A=4.0). The plasma current is relatively low (I p =11.32 MA) and bootstrap current fraction is high (f BC =0.88). Consequently, the auxiliary power required for RF current drive is relatively low (∝80 MW). At the same time, the average toroidal beta is high (β=5%), providing power densities near practical engineering limits (the peak neutron wall loading is 5.7 MW m -2 ). The toroidal-field (TF) coil system is designed with relatively 'conventional' materials (Nb 3 Sn and NbTi conductor with 316SS structures), and is operated at a design limit of ∝16 T at the coil in order to optimize the design point. The ARIES-RS design uses a self-cooled lithium blanket with vanadium alloy as the structural material. The V-alloy has low activation, low afterheat, high temperature capability and can handle high heat flux. A self-cooled liquid lithium blanket is simple, and with the development of an insulating coating, has low operating pressure. Also, this blanket gives excellent neutronics performance. Detailed analysis has been performed to minimize the cost and maximize the performance of the blanket and shield. (orig.)

  4. Study of time-critical diagnostic method for emergency operation of nuclear power plant

    Gofuku, A.; Yoshikawa, H.; Itoh, K.; Wakabayashi, J.

    1986-01-01

    In order to support the emergency operation of nuclear power plant, the method of time-critical diagnostic plant analyzer has been investigated. The conception of the emergency operation support center is proposed and two types of plant analyzer may be installed in this center. One analyzer is a real-time tracking simulation code using the observed signals and another is a fast trend-prediction code. A real-time tracking code, TOKRAC, has been developed for analyzing the PWR primary loop thermo-hydraulics at SBLOCA, and the applicability of this code was examined by the numerical experiments for the initial phase transient of both TMI-2 accident and 6% coldleg SBLOCA of a Westinghouse-type PWR plant. The results showed that fairly good tracking was carried out by TOKRAC. The CPU time of TOKRAC was about 12-14 percent of real-time

  5. Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

    Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

  6. Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

    Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

  7. Survey of seismic fragilities used in PRA studies of nuclear power plants

    Park, Y.J.; Hofmayer, C.H.; Chokshi, N.C.

    1998-01-01

    In recent years, seismic PRA studies have been performed on a large number of nuclear power plants in the USA. This paper presents a summary of a survey on fragility databases and the range of evaluated fragility values of various equipment categories based on past PRAs. The survey includes the use of experience data, the interpretations of available test data, and the quantification of uncertainties. The surveyed fragility databases are limited to data available in the public domain such as NUREG reports, conference proceedings and other publicly available reports. The extent of the availability of data as well as limitations are studied and tabulated for various equipment categories. The survey of the fragility values in past PRA studies includes not only the best estimate values, but also the dominant failure modes and the estimated uncertainty levels for each equipment category. The engineering judgments employed in estimating the uncertainty in the fragility values are also studied. This paper provides a perspective on the seismic fragility evaluation procedures for equipment in order to clearly identify the engineering analysis and judgment used in past seismic PRA studies

  8. Study on integrity evaluation of structures associated with nuclear power plants

    NONE

    2013-08-15

    The 3.11 Tohoku District -off the Pacific Ocean Earthquake and tsunami made us observations of tsunami height in large exceedance of the design, and besides it gave the most damages to several nuclear power plants facing the Pacific Ocean at source area of the earthquake. Particularly, at Fukushima-Daiichi Nuclear Power Plant, the great tsunami caused the simultaneous failure on several plant's equipment and components, which escalated into the core damage. Considering these background, the objective of this research is to enhance fundamental technology relative to integrity evaluation of SSC's (System, Structure, components) targeting external events such as earthquakes and tsunamis. Specifically, it is performed to develop structure evaluation methods against tsunami, to develop seismic isolation system, and to enhance non-liner analysis methods for building and so on. In viewpoint of the other external events except earthquake and tsunami, it was performed to develop impact analysis methods on building and outdoor structure against swept things caused by tornadoes. After that on the basis of these developments, it is performed to draw up guidelines such as the base isolation structure review guide, and the structure design and risk evaluation guide against tsunami, which are to be used in cross-check analysis targeting integrity evaluation of nuclear power plant's structures against external events such as earthquakes and tsunamis. (author)

  9. Study on integrity evaluation of structures associated with nuclear power plants

    2013-01-01

    The 3.11 Tohoku District -off the Pacific Ocean Earthquake and tsunami made us observations of tsunami height in large exceedance of the design, and besides it gave the most damages to several nuclear power plants facing the Pacific Ocean at source area of the earthquake. Particularly, at Fukushima-Daiichi Nuclear Power Plant, the great tsunami caused the simultaneous failure on several plant's equipment and components, which escalated into the core damage. Considering these background, the objective of this research is to enhance fundamental technology relative to integrity evaluation of SSC's (System, Structure, components) targeting external events such as earthquakes and tsunamis. Specifically, it is performed to develop structure evaluation methods against tsunami, to develop seismic isolation system, and to enhance non-liner analysis methods for building and so on. In viewpoint of the other external events except earthquake and tsunami, it was performed to develop impact analysis methods on building and outdoor structure against swept things caused by tornadoes. After that on the basis of these developments, it is performed to draw up guidelines such as the base isolation structure review guide, and the structure design and risk evaluation guide against tsunami, which are to be used in cross-check analysis targeting integrity evaluation of nuclear power plant's structures against external events such as earthquakes and tsunamis. (author)

  10. Application of sensitivity analysis in nuclear power plant probabilistic risk assessment studies

    Hirschberg, S.; Knochenhauer, M.

    1986-01-01

    Nuclear power plant probabilistic risk assessment (PRA) studies utilise many models, simplifications and assumptions. Also subjective judgement is widely applied due to lack of actual data. This results in significant uncertainties. Three general types of uncertainties have been identified: (1) parameter uncertainties, (2) modelling uncertainties, and (3) completeness uncertainties. The significance of some of the modelling assumptions and simplifications cannot be investigated by assignment and propagation of parameter uncertainties. In such cases the impact of different options may (and should) be studied by performing sensitivity analyses, which concentrate on the most critical elements. This paper describes several items suitable for close examination by means of application of sensitivity analysis, when performing a level 1 PRA. Sensitivity analyses are performed with respect to: (1) boundary conditions (success criteria, credit for non-safety systems, degree of detail in modelling of support functions), (2) operator actions, (3) treatment of common cause failures (CCFs). The items of main interest are continuously identified in the course of performing a PRA study, as well as by scrutinising the final results. The practical aspects of sensitivity analysis are illustrated by several applications from a recent PRA study. The critical importance of modelling assumptions is also demonstrated by implementation of some modelling features from another level 1 PRA into the reference model. It is concluded that sensitivity analysis leads to insights important for analysts, reviewers and decision makers. (author)

  11. A study on the human factors of nuclear power plants man-machine interface

    Shin, Hyun Kook; Lee, Jeong Woon; Lee, Yong Hee; Oh, In Suk; Park, Geun Ok

    1991-01-01

    Approaches of the MMIS design were analysed in this project. Both systems approach and experimental approach were studied. In addition, guidelines for the design of MMI are discussed. The methodology of experimental approach studied in this project can be useful for establishing experimental criteria on MMI design items. The framework of a computer code was developed by utilizing function-based task analysis and procedure information requirements. This can be further developed as a tool useful for the verification and validation of MMI designs. A test facility was designed in compliance with the purpose of experimental approach by considering specific conditions and factors inherent in nuclear power plants. Test facility can be used for conducting experiments which provide detailed human performance and characteristics data at the low level of systems approach. An experimental study was performed to obtain a range of illumination levels suitable for the operation in VDU-based control rooms. Existing design guidelines were tested by this experimental study. A conceptual design of MMIS was developed in accordance with the established MMIS design approach and was evaluated through the comparison to other advanced control room designs. (Author)

  12. A Study on the Evaluation Technology of Welds Integrity in Nuclear Power Plants

    Chang, Hyun Young; Kim, Jong Sung; Jin, Tae Eun

    2007-01-01

    The final goal of this study is to develop the core technologies applicable to the design, operation and maintenance of welds in nuclear structures. This study includes predicting microstructure changes and residual stress for welded parts of nuclear power plant components. Furthermore, researches are performed on evaluating fatigue, corrosion, and hydrogen induced cracking and finally constructs systematically integrated evaluation system for structural integrity of nuclear welded structures. In this study, metallurgical and mechanical approaches have been effectively coordinated considering real welding phenomena in the fields of welds properties such as microstructure, composition and residual stress, and in the fields of damage evaluations such as fatigue, corrosion, fatigue crack propagation, and stress corrosion cracking. Evaluation techniques tried in this study can be much economical and effective in that it uses theoretical/semi-empirical but includes many additional parameters that can be introduced in real phenomena such as phase transformation, strength mismatch and residual stress. It is clear that residual stress makes great contribution to fatigue and stress corrosion cracking. Therefore the mitigation techniques have been approached by reducing the residual stress of selected parts resulting in successful conclusions

  13. Radiochemistry in nuclear power plants

    Schwarz, W.

    2007-01-01

    Radiochemistry is employed in nuclear power plants not as an end in itself but, among other things, as a main prerequisite of optimum radiation protection. Radiochemical monitoring of various loops provides important information about sources of radioactivity, activity distribution in the plant and its changes. In the light of these analytical findings, plant crews are able to take measures having a positive effect on radiation levels in the plant. The example of a BWR plant is used to show, among other things, how radiochemical analyses helped to reduce radiation levels in a plant and, as a consequence, to decrease clearly radiation exposure of the personnel despite higher workloads. (orig.)

  14. Study on a heat recovery system for the thermal power plant utilizing air cooling island

    Sun, Jian; Fu, Lin; Sun, Fangtian; Zhang, Shigang

    2014-01-01

    A new heat recovery system for CHP (combined heat and power) systems named HRU (heat recovery unit) is presented, which could recover the low grade heat of exhausted steam from the turbine at the thermal power plant directly. Heat recovery of exhausted steam is often accomplished by recovering the heat of cooling water in current systems. Therefore, two processes of heat transfer is needed at least. However, exhausted steam could be condensed in the evaporator of HRU directly, which reduce one process of heat transfer. A special evaporator is designed condense the exhausted steam directly. Simulated results are compared to experiments, which could include the calculation of heat transfer coefficients of different parts of HRU. It is found that about 25Mw of exhausted steam is recovered by this system. HRU could be promising for conventional CHP systems, which could increase the total energy efficiency obviously and enlarge the heating capacity of a built CHP system. - Highlights: • A new heat recovery system for thermal power plant is presented. • A mathematical model including heat transfer coefficients calculation is given. • This heat recovery system is experimented at a thermal power plant. • Performances of this system under different working conditions are simulated

  15. Characterization study of cesium concentrated particles in the soils near the Fukushima Daiichi nuclear power plant

    Satou, Yukihiko; Sueki, Keisuke; Sasa, Kimikazu; Adachi, Kouji; Igarashi, Yasuhito

    2015-04-01

    Radionuclides from the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident contaminated a vast area. Two types of contamination, spread and spot types, were observed in soils with autoradiography using an imaging plate. Other samples such as dust filters, vegetation, X-ray films, and so on, also indicate the spot type contamination in the early stage of the FDNPP accident. The source of spot type contamination is well known as hot particles at the Chernobyl Nuclear Power Plant (ChNPP) accident in 1986. Hot particles were divided into two groups, fuel hot particles and fission product particles, and they were emitted directly from reactor core with phreatic explosion and fire. In contrast, the official reports of the FDNPP accident did not conforme core explosion. In addition, the emitted total amount of Uranium was very few (Yamamoto et al., 2014). Thus, the spot type contaminations were not identified as the same of hot particles yet. Therefore, the present study aimed to pick up and identify the spot contaminations in soils. Surface soil samples were collected at 20 km northwest from the FDNPP in June 2013. Soils were spread in plastic bags for autoradiography with imaging plate analysis. Then, the soil particles were collected on a sticky carbon tape and analyzed by SEM-EDS to detect radioactive particles. Finally, particles were confirmed to contain photo peaks in the γ-spectrum by a germanium semiconductor detector. Four radioactive particles were isolated from the soil samples in the present study. Detected γ-ray emission radionuclides were only Cs-134 and Cs-137. The X-ray spectra on the SEM-EDS of all particles showed a Cs peak as well as O, Fe, Zn, and Rb peaks, and these elements were distributed uniformly within the particles. In addition, uniform distribution of Si was also shown. Moreover, U was detected from one of the particles, but U concentration was very low and existed locally in the particle. These characters are very similar to previous

  16. Preliminary Study on Effect of Aviation Fuel in the Safety Evaluation of Nuclear Power Plant Crashed by Aircraft

    Jin, Byeong Moo; Jeon, Se Jin; Lee, Yun Seok; Kim, Young Jin

    2011-01-01

    As the safety assessments of nuclear power plants for the hypothetical large civil aircraft crash should be made mandatory, studies on large aircraft-nuclear power plant impact analyses and assessments are actively in progress. The large civil aircraft are being operated with a large amount of fuel and the fuel can be assumed to contribute to the impact loads at the impact. The fuel, i.e., the internal liquid can be considered as added masses classically in the evaluation of the impact load. According to the recent experimental research, it has been shown that the impact load of high speed impacting body with internal liquid is much higher than that of the mass-equivalent impacting body. In this study, the impact loads according to the existence of the internal liquid are computed by numerical methods and the safety assessment of nuclear power plant crashed by large civil aircraft are performed as an application

  17. Assessment Studies regarding the Optimal Sizing of Wind Integrated Hybrid Power Plants for Off-Grid Systems

    Petersen, Lennart; Iov, Florin; Tarnowski, German Claudio

    2018-01-01

    The paper focusses on the optimal sizing of off-grid hybrid power plants including wind power generation. A modular and scalable system topology as well as an optimal sizing algorithm for the HPP has been presented in a previous publication. In this paper, the sizing process is evaluated by means...... of assessment studies. The aim is to address the impact of renewable resource data, the required power supply availability and reactive power load demand on the optimal sizing of wind integrated off-grid HPPs....

  18. Mercury Speciation in Coal-Fired Power Plant Flue Gas-Experimental Studies and Model Development

    Radisav Vidic; Joseph Flora; Eric Borguet

    2008-12-31

    The overall goal of the project was to obtain a fundamental understanding of the catalytic reactions that are promoted by solid surfaces present in coal combustion systems and develop a mathematical model that described key phenomena responsible for the fate of mercury in coal-combustion systems. This objective was achieved by carefully combining laboratory studies under realistic process conditions using simulated flue gas with mathematical modeling efforts. Laboratory-scale studies were performed to understand the fundamental aspects of chemical reactions between flue gas constituents and solid surfaces present in the fly ash and their impact on mercury speciation. Process models were developed to account for heterogeneous reactions because of the presence of fly ash as well as the deliberate addition of particles to promote Hg oxidation and adsorption. Quantum modeling was used to obtain estimates of the kinetics of heterogeneous reactions. Based on the initial findings of this study, additional work was performed to ascertain the potential of using inexpensive inorganic sorbents to control mercury emissions from coal-fired power plants without adverse impact on the salability fly ash, which is one of the major drawbacks of current control technologies based on activated carbon.

  19. Linguistic control of a nuclear power plant

    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

  20. Automation technology in power plants

    Essen, E.R.

    1995-01-01

    In this article a summery of the current architecture of modern process control systems in power plants and future trends have been explained. The further development of process control systems for power plants is influenced both by the developments in component and software technologies as well as the increased requirements of the power plants. The convenient and low cost configuration facilities of new process control systems have now reached a significance which makes it easy for customers to decide to purchase. (A.B.)

  1. Study on in-core fuel management for CNP1500 nuclear power plant

    Li Dongsheng

    2005-10-01

    CNP1500 is a four-loop PWR nuclear power plant with light water as moderator and coolant. The reactor core is composed of 205 AFA-3GXL fuel assemblies. The active core height at cold is 426.4 cm and equivalent diameter is 347.0 cm. The reactor thermal output is 4250 MW, and average linear power density is 179.5 W/cm. The cycle length of equilibrium cycle core is 470 equivalent full power days. For all cycles, the moderator temperature coefficients at all conditions are negative values, the nuclear enthalpy rise factors F ΔH at hot full power, all control rods out and equilibrium xenon are less than the limit value, the maximum discharge assembly burnup is less 55000 MW·d/tU, and the shutdown margin values at the end of life meet design criteria. The low-leakage core loading reduces radiation damage on pressure vessel and is beneficial to prolong use lifetime of it. The in-core fuel management design scheme and main calculation results for CNP1500 nuclear power plant are presented. (author)

  2. Lay-out of the He-cooled solid breeder model B in the European power plant conceptual study

    Hermsmeyer, S.; Malang, S.; Fischer, U.; Gordeev, S.

    2003-01-01

    The European helium cooled pebble bed (HCPB) blanket concept is the basis for one of two limited-extrapolation plant models that are being elaborated within the European power plant conceptual study (PPCS). In addition to addressing the case for fusion safety and environmental compatibility, following earlier studies like SEAFP or SEAL, this reactor study puts emphasis on plant availability and economic viability, which are closely related to specific plant models and require a detailed lay-out of the fusion power core and a consideration of the overall plant (balance of plant). Within the development of in-vessel components for the plant model, the major tasks to be carried out were: (i) adaptation of the HCPB concept--featuring separate pebble beds of ceramic breeder and Beryllium neutron multiplier and reduced-activation ferritic-martensitic steel EUROFER as structural material--to the large module segmentation chosen for reasons of plant availability in part II of the PPCS; (ii) proposal of a concept for a Helium cooled divertor compatible with a maximum of 10 MW/m 2 heat flux to satisfy the requirements of reasonably extrapolated plasma physics; (iii) lay-out of the major plant model components and integration into the in-vessel dimensions found from system code calculations for a power plant of 1500 MW electrical output and iterated data on the plant model performance. The paper defines all major in-vessel components of plant model B, as it is called in the PPCS, namely (i) the unit of FW, blanket and high temperature shield that is to be replaced regularly; (ii) the low temperature shield that is laid out as a lifetime component of the reactor; (iii) the divertor; and (iv) the in-vessel manifolding. Results are presented for the thermal-hydraulic performance of the components and for the thermal-mechanical behaviour of the blanket and the divertor target plate. These results suggest, together with results from the wider exploration of the plant model within

  3. Building a new nuclear power plant in Finland? Studies performed. Annex 2

    Patrakka, E.

    2002-01-01

    The electricity consumption per capita is high in Finland due to the country's industrial structure and to the climatic conditions. Industry consumes 55% of the electricity in Finland. The demand of electricity is expected to grow at a rate of 1.5% a year until 2010, and further at a yearly rate of 1% until 2015. This will require 3800 MW of new generating capacity by 2015. A recent study indicates that in base-load power production in Finland the generating costs of a nuclear plant are the lowest in comparison with generation using coal, natural gas or peat. The difference to coal would be 9%, to gas 18% and to peat 40%. The target for Finland to reduce greenhouse gas emissions under the EU burden sharing is 0%. In comparison with business as usual scenarios, however, the reduction need is of the magnitude of 20%, one of the hardest in the EU. Finland already has taken into use the methods, which now are considered essential within the EU for reducing the CO 2 releases. Teollisuuden Voima Oy (TVO) submitted on 15 November 2000 to the Council of State an application for a decision in principle concerning the construction of additional nuclear capacity. The submission of the application is reasoned by the shareholders' need for additional electricity. Furthermore, nuclear power, together with renewable energy sources, makes it possible to comply with the Kyoto protocol commitments. The actual investment decision can be made first after a positive decision in principle has been received from the Council of State and the Parliament. The submission of the application was preceded by a number of studies, the contents of which are summarised. (author)

  4. Man and nuclear power plants

    Anon.

    1978-01-01

    According to the Inst. fuer Unfallforschung/TUeV Rheinland, Koeln, the interpretation of empirical data gained from the operation of nuclear power plants at home and abroad during the period 1967-1975 has shown that about 38% of all reactor accidents were caused by human failures. These occured either during the design and construction, the commissioning, the reconditioning or the operation of the plants. This very fact stresses human responsibility for the safety of nuclear power plants, in spite of those plants being automated to a high degree and devices. (orig.) [de

  5. Owners of nuclear power plants

    Hudson, C.R.; White, V.S.

    1996-11-01

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

  6. Owners of nuclear power plants

    Wood, R.S.

    1979-12-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of December 1, 1979. The list includes all plants licensed to operate, under construction, docketed for NRC safety and envionmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally cancelled. In many cases, ownership may be in the process of changing as a result of antitrust license conditions and hearings, altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified

  7. Studies of S-CO{sub 2} Power Plant Pipe Design

    Kim, Minseok; Ahn, Yoonhan; Lee, Jeong Ik [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-05-15

    Further development of nuclear energy is required to address the global warming issue while overcoming the difficulty of meeting the constantly growing demand of energy. As the nuclear energy does not only reduce the carbon dioxide emission but also attain sufficient and stable electricity supply, this is considered as one of the most clean and sustainable energy sources. The Sodium-cooled Fast Reactor (SFR) is a strong candidate among the next generation nuclear reactors. However, current SFR design may face difficulty in public acceptance due to the potential hazard from sodium-water reaction (SWR) when the current conventional steam Rankine cycle is utilized as a power conversion system for SFR. In order to eliminate SWR, the Supercritical CO{sub 2} (S-CO{sub 2}) cycle has been proposed. Although many S-CO{sub 2} cycle concepts are being suggested by many research organizations, pipe selection criteria for S-CO{sub 2} cycle are one of the areas that are not clearly established. As one of the most important parts of the plant design is economical fluid transfer, this paper will discuss how to select a suitable pipe for the S-CO{sub 2} power plant compared to steam Rankine cycle. The main advantages of S-CO{sub 2} cycle are: prevention of no SWR by changing the working fluid, relatively high efficiency with 450∼750 .deg. C turbine inlet temperature, physically compact size. Additional study for larger system such as 300MW class system in MIT report will be conducted. From the preliminary estimation when the S-CO{sub 2} system becomes large than the pipe diameter may exceed the current ASME standard. This means that more innovative approach will be needed for the S-CO{sub 2} pipe design. To economically design the pipe of S-CO{sub 2} recompressing cycle, optimal flow velocity for S-CO{sub 2} that can be obtained through the process engineering should exist. Although the Ronald W. Capps equation offers an optimal flow velocity while considering safety, capital

  8. Feasibility study for biomass power plants in Thailand. Volume 2. appendix: Detailed financial analysis results. Export trade information

    1997-01-01

    This study, conducted by Black and Veatch, was funded by the U.S. Trade and Development Agency. The report presents a technical and commercial analysis for the development of three nearly identical electricity generating facilities (biomass steam power plants) in the towns of Chachgoengsao, Suphan Buri, and Pichit in Thailand. Volume 2 of the study contains the following appendix: Detailed Financial Analysis Results

  9. Research of the Power Plant Operational Modes

    Koismynina Nina M.

    2017-01-01

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

  10. Competitive breeder power plants

    Winkleblack, R.K.

    1984-01-01

    To utilize the fissile material that is accumulating in the utilities' spent fuel pools, breeder plants must be less expensive than current LWR costs (or utilities will not buy nuclear plants in the near future) and also be highly reliable. The fundamental differences between LWRs and LMFBRs are discussed and recommendations are made for making the most of these differences to design a superior breeder plant that can sell in the future, opening the way to U.S. utilities becoming self-sufficient for fuel supply for centuries

  11. Examining work structure in nuclear power plants

    Bauman, M.B.; Boulette, M.D.; Van Cott, H.P.

    1985-01-01

    This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured ''critical incident'' interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program

  12. Shaking table test study on seismic performance of dehydrogenation fan for nuclear power plants

    Liu Kaiyan; Shi Weixing; Cao Jialiang; Wang Yang

    2011-01-01

    Seismic performance of the dehydrogenation fan for nuclear power plants was evaluated based on the shaking table test of earthquake simulation. Dynamic characteristics including the orthogonal tri-axial fundamental frequencies and equivalent damping ratios were measured by the white noise scanning method. Artificial seismic waves were generated corresponding to the floor acceleration response spectra for nuclear power plants. Furthermore, five OBE and one SSE shaking table tests for dehydrogenation fan were performed by using the artificial seismic waves as the seismic inputs along the orthogonal axis simultaneity. Operating function of dehydrogenation fan was monitored and observed during all seismic tests, and performance indexes of dehydrogenation fan were compared before and after seismic tests. The results show that the structural integrity and operating function of the dehydrogenation fan are perfect during all seismic tests; and the performance indexes of the dehydrogenation fan can remain consistent before and after seismic tests; the seismic performance of the dehydrogenation fan can satisfy relevant technical requirements. (authors)

  13. Measuring the environmental costs of tidal power plant construction: A choice experiment study

    Lee, Joo-Suk; Yoo, Seung-Hoon

    2009-01-01

    Korea is considering the construction of a tidal power plant (TPP) at Garolim Bay. However, as the construction of the Garolim TPP (GTPP) is expected to entail some environmental damage, it has become an increasingly important topic for public debate. Using a choice experiment (CE) approach, this study attempts to measure the economic cost that results from the environmental damage caused by the construction of GTPP. The CE is used to measure the environmental costs of individual attributes, including the reduction in the area of the tidal flat, the degradation of seawater quality, and the destruction of marine life. The results indicate that the annual willingness to pay (WTP) per household for mitigating the environmental damage that results from the worst-possible situation in relation to the present situation is about 96,042 Korean won (USD 101.1) in the seven biggest cities (off-site regions) and 18,584 Korean won (USD 19.6) in Seosan and Taean (on-site regions). This study is expected to provide policy-makers with quantitative information that will be useful to decide whether or not GTPP should be constructed.

  14. Sealing of rock joints by induced calcite precipitation. A case study from Bergeforsen hydro power plant

    Hakami, E.; Qvarfort, U.; Ekstav, A.

    1991-01-01

    The possibilities of sealing rock fractures by injecting water saturated with calcite solution, and hereby inducing a calcite precipitation inside the fracture, is investigated. The way of reaction and the amount of calcite precipitation will depend on the saturation of calcium carbonate in the water, the temperature, the pH and the CO 2 -pressure. There is experience of lime-saturated water injection in the rock foundation below the dam at Bergeforsens power plant (1955-1968). It was observed that the consumption of injected lime water decreased with time. A possible reason to the decrease in lime water consumption is that calcite has precipitated such that the permeability of the rock in general is lowered. Another explanation to this could be that calcite precipitation is concentrated to the fractures surrounding the injection holes, thus preventing the lime water from penetrating further into the rock. It is recommended that further studies of the fracture fillings in drill cores from Bergeforsen is performed. The aim of such study should be to determine the extent of induced calcite precipitation and to investigate its chemical and physical properties. (authors)

  15. Workplace monitoring and occupational health studies in the Sostanj thermal power plant, Slovenia

    Jacimovic, R.; Falnoga, I.; Jeran, Z.; Kump, P.; Necemer, M.; Stropnik, B.; Kobal, A.B.

    2000-01-01

    Only a few investigations have been performed in the Sostanj Thermal Power Plant (TPP) involving comprehensive studies of trace and minor elements and radionuclides in the workplaces. Workers at the TPP in some sectors are exposed to high levels of coal dust, in others to dusty operations with ash and electrostatically precipitated fly ash, and in addition a force of welders is employed for maintenance and construction tasks. Welders work 5 to 6 hours per day and they are protected only from UV light. They are exposed to high concentrations of metals in inhaled welding fume. One method to determine the levels of trace and minor elements in the atmosphere at the working places is to sample aerosols. Aerosols were collected on Nuclepore polycarbonate membrane filters by a Casella personal sampler at different working places in the Sostanj TPP. In this report, the emphasis is on the methodology and analytical development (instrumental neutron activation analysis and X-ray spectrometry), and to a lesser extent on the results obtained up to now. Results obtained by the k 0 -method and XRF techniques for aerosols collected at different working places in the Sostanj TPP are presented and discussed. Results obtained for an intercomparison study for different samples provided by IAEA are not presented in this progress report but have been sent to the IAEA and the National Institute of Occupational Health (Denmark)

  16. Study on comprehensive evaluation model for nuclear power plant control room layout

    Zhu Yiming; Liu Yuan; Fan Huixian

    2010-01-01

    A comprehensive evaluation model for layout of the main control room of nuclear power plants was proposed. Firstly the design scope and principle for the layout of the main control room were defined based on the standards, and then the index system for the comprehensive evaluation was established. Finally, comprehensive evaluation was carried out for the layout design by applying the fuzzy comprehensive evaluation method in the index system. (authors)

  17. Preliminary study of the environmental radiological assessment for the Garigliano nuclear power plant decommissioning

    Esposito, A.M.; Sabbarese, C.; Sirignano, C.; Visciano, L.; D'Onofrio, A.D.; Lubritto, C.; Terrasi, F.

    2002-01-01

    In the last few years many nuclear installations in the world have been stopped either because they reached the end of production lifetime, or for operation problems or, like in Italy, for political decisions. This stop started the decommissioning procedure. It consists in the dismantling of the nuclear installation with appropriate controls and limitations of environmental and radiological impact which arises from these operations. The evaluation of risk and the actions needed for the population safeguard are generally inspired to the recommendations of the International Commission on Radiological Protection (ICRP), but each country faces the problem with different evaluation methodologies and calculations. That is due to different laws and environmental, social and economical context where nuclear installations are located. For this, the decommissioning operations must be separately evaluated for each nuclear installation. In this paper, we present the work carried out so far about the decommissioning of the Nuclear Power Plant of Garigliano (Caserta, Italy), which is managed by SoGIN (Societa di Gestione degli Impianti Nucleari). This Nuclear Power Plant began its activity in 1964 by using a boiling water reactor with a production of 160 MW electric power. In 1979 this nuclear installation was stopped for maintenance and operation has not been resumed until the referendum in 1986, after which all Italian nuclear plants were stopped. Now, the Nuclear Power Plant of Garigliano has the reactor isolated respect to the remaining part and all components and pipes have been drained and sealed. The underground tanks of radioactive wastes have been evacuated and decontaminated. The radioactive wastes have been completely conditioned with cementification in drums suitable to prevent outside release

  18. A study for the establishment of regulatory requirement and evaluation guide for station blackout in nuclear power plants

    Lim, J. H.; Koo, C. S.; Joo, W. P.; Oh, S. H.; Shin, W. K.

    1999-01-01

    The consequence of SBO event could be a severe accident unless AC power was restored within a proper time, because many safety systems depend upon AC power. Based on the severity, the SBO has been extensively studied since it was identified as Unresolved Safety Issue at USNRC. The resolution of those studies is a rule-making such as 10 CFR 50.63 and Regulatory Guide 1.155. But there is no regulatory requirements of SBO for an operating domestic nuclear power plant up to the present time. This tudy has established SBO rule(regulatory requirements and evaluation guides) for an operating PWR type of the operating nuclear power plants in Korea

  19. Modelling of nuclear power plant decommissioning financing.

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  20. Study on the utilization of the cognitive architecture EPIC to the task analysis of a nuclear power plant operator

    Soares, Herculano Vieira

    2003-02-01

    This work presents a study of the use of the integrative cognitive architecture EPIC - Executive-Process - Interactive-Control, designed to evaluate the performance of a person performing tasks in parallel in a man-machine interface, as a methodology for Cognitive Task Analysis of a nuclear power plant operator. A comparison of the results obtained by the simulation by EPIC and the results obtained by application of the MHP model to the tasks performed by a shift operator during the execution of the procedure PO-E-3 - Steam Generator Tube Rupture of Angra 1 Nuclear Power Plant is done. To subsidize that comparison, an experiment was performed at the Angra 2 Nuclear Power Plant Full Scope Simulator in which three operator tasks were executed, its completion time measured and compared with the results of MHP and EPIC modeling. (author)

  1. Conceptual design study of the moderate size superconducting spherical tokamak power plant

    Gi, Keii; Ono, Yasushi; Nakamura, Makoto; Someya, Youji; Utoh, Hiroyasu; Tobita, Kenji; Ono, Masayuki

    2015-06-01

    A new conceptual design of the superconducting spherical tokamak (ST) power plant was proposed as an attractive choice for tokamak fusion reactors. We reassessed a possibility of the ST as a power plant using the conservative reactor engineering constraints often used for the conventional tokamak reactor design. An extensive parameters scan which covers all ranges of feasible superconducting ST reactors was completed, and five constraints which include already achieved plasma magnetohydrodynamic (MHD) and confinement parameters in ST experiments were established for the purpose of choosing the optimum operation point. Based on comparison with the estimated future energy costs of electricity (COEs) in Japan, cost-effective ST reactors can be designed if their COEs are smaller than 120 mills kW-1 h-1 (2013). We selected the optimized design point: A = 2.0 and Rp = 5.4 m after considering the maintenance scheme and TF ripple. A self-consistent free-boundary MHD equilibrium and poloidal field coil configuration of the ST reactor were designed by modifying the neutral beam injection system and plasma profiles. The MHD stability of the equilibrium was analysed and a ramp-up scenario was considered for ensuring the new ST design. The optimized moderate-size ST power plant conceptual design realizes realistic plasma and fusion engineering parameters keeping its economic competitiveness against existing energy sources in Japan.

  2. Investigation Study on Gamma Ray Imaging Technology for Nuclear Power Plant Decommissioning

    Lee, Sang Guk; Jeong, Woo Tae [Machinery and Materials Laboratory, Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2014-10-15

    The gamma ray imaging system provides an estimated dose-rate of the source at 30 cm above. The gamma detector is a terbium activated glass scintillator. The system is capable of producing a color two dimensional image of a radiation field superimposed on a black and white visual image. The system used in US power plants consists of a portable sensor head that contains both gamma ray and visual imaging systems and a portable control computer. The gamma ray imaging system has been successfully used as an ALARA tool for identifying source terms and determining the adequacy of existing shielding. Because the control system can be positioned away from the camera, the radiation exposure to personnel can be reduced without extensive shielding requirements. The gamma ray imaging system has been used to date in the decommissioning of Maine Yankee, Big Rock point,Trojan, San Onofre1, and Millstone 1. The equipment has also been used at normal refueling outages at a number of commercial nuclear power plants and at several Department of Energy Decommissioning sites. This paper is intended to review the applicability of gamma ray imaging system as decommissioning tool. In order to review the actual applicability, we are going to introduce applications for US power plants.

  3. A comparative study of imbalance reduction strategies for virtual power plant operation

    Zapata, J.; Vandewalle, J.; D'haeseleer, W.

    2014-01-01

    The penetration of a large amount of distributed generation (DG) technologies with intermittent output, such as photovoltaic installations and wind turbines, yields an important challenge to the electric grid. It is believed that aggregating them with controllable technologies such as cogeneration devices (CHP) can help to balance fluctuations of renewable energy. This work evaluates the ability of a virtual power plant (VPP) to reduce the imbalance error of renewable generators. The study is undertaken in a VPP that consists of several cogeneration devices and photovoltaic (PV) installations. The virtual power plant operator bids electricity into the day-ahead market using the forecast for solar irradiation and for the thermal demand. During the actual day, the imbalance due to deviations between the forecasted electricity delivered and the real output has to be settled in the balancing market. Thus, in order to compensate these errors and possible economic drawbacks, the operation of the CHP is adjusted periodically in a so called reschedule. Two different rescheduling strategies are compared against a ‘reference scenario’ in which the imbalance error is settled in the market. The first one (‘forced strategy’) aims at reducing the imbalance error every time step regardless of the imbalance prices. The second (‘economic strategy’) considers the imbalance prices and takes only action if it is economically appropriate and thus intends to reduce the total operational cost. The results show that the rescheduling technique is able to reduce the imbalance error (up to 90% depending on the season and the strategy). Additionally, the total operational cost is estimated. However, the nowadays imbalance prices only lead to a minor financial advantage that is unlikely to motivate real life operators to perform a rescheduling strategy. - Highlights: • The VPP is dispatched by a day-ahead optimization followed by a rescheduling. • A forced rescheduling strategy

  4. Space nuclear reactor power plants

    Buden, D.; Ranken, W.A.; Koenig, D.R.

    1980-01-01

    Requirements for electrical and propulsion power for space are expected to increase dramatically in the 1980s. Nuclear power is probably the only source for some deep space missions and a major competitor for many orbital missions, especially those at geosynchronous orbit. Because of the potential requirements, a technology program on space nuclear power plant components has been initiated by the Department of Energy. The missions that are foreseen, the current power plant concept, the technology program plan, and early key results are described

  5. Literature study regarding fire protection in nuclear power plants. Part I: Fire rated separations

    Isaksson, S.

    1995-06-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Conventional building codes can not give guidance on where to make fire rated separations in order to separate redundant trains of safety systems. The separation must originate in functional demands from the authorities on what functions are essential during and after a fire, and under what circumstances these functions shall be retained, i.e. the number of independent faults and initiating events. As a basic demand it is suggested to rate the strength of separations according to conventional building code, based on fire load. The whole separating construction shall have the same fire rating, including the ventilation system. Deviations from the basic demand can de done in case it can be proven that it is possible to compensate some or all of the fire rating with other measures. There is a general lack of statistical information regarding the reliability of fire separating constructions such as walls, fire doors, penetration seals and fire dampers. The amount of cables penetrating a seal is in many cases much higher in real installations than what has been tested for type approval. It would therefore be valuable to perform a furnace test with a more representative amount of cables passing through a penetration seal. Tests have shown that the 20 foot horizontal separation distance stipulated by NRC is not a guarantee against fire damage. Spatial separations based on general requirements shall not be allowed, but considered from case to case based on actual circumstances. For fire protection by isolation or coatings, it is of great importance to choose the method of protection carefully, to be compatible with the material it shall be applied on, and the environment and types of fire that may occur. 48 refs, 2 figs, 5 tabs

  6. Air pollution reduction in thermoelectric power stations - case study: Iquitos power plant; Reducao do impacto da poluicao do ar em usinas termeletricas - estudo de caso: usina termeletrica Iquitos

    Dondero, Luz [Sao Paulo Univ., SP (Brazil). Inst. de Energia e Eletrotecnica. Programa Interunidades de Pos-graduacao em Energia]. E-mail: luz@iee.usp.br

    2000-07-01

    This work studies the environmental impacts of atmospheric emissions sent out by the Iquito's thermoelectric power station in Peru. Initially, we compute the quantitative flows (in g/s) of major gas pollutants (SO{sub 2}, SO{sub 3}, NOx, CO, CO{sub 2} and MP) emitted by the power plant. Then, we calculate the station's emission rates per kWh generated (in kilogram of pollutant /kWh). Having those inputs, we adopt EPA's SCREEN3.0 dispersion model to simulate the SO{sub 2} and NOx into the local atmosphere. We also forecast the future evolution of SO{sub 2} emissions considering the potential growth of electricity generation in the power plant. Since the Iquito's power station is located within the city's urban area, with gas emissions having direct impacts upon the local population, we study different strategies for emissions reduction from the plant. Firstly, we consider the upgrading of the existing plant with additional equipment for a more strict emission control. Then, we analyze the option of shutting down the most critical machine (in terms of atmospheric emission) in the old plant, and its substitution by a new and more efficient machine. We concluded that, although the addition of more strict control equipment is more efficient on reducing total emission, the strategy of exchanging machines is less costly and should be consider as the preferable option. (author)

  7. A study on the implementation of an integrated Environmental Qualification Management System(EQMS) for nuclear power plant

    Bhang, Keug Jin; Jeong, Sun Chul; Kang, Pil Sun [KHNP CRI, Daejeon (Korea, Republic of)

    2012-10-15

    Environmental Qualification Management System(EQMS) for Nuclear Power Plant is a web based program for preventing degradation and managing original functions of environmental qualification equipment during nuclear power plant life cycle by inspecting and improving status of them periodically. But cognitive issues have stayed in the construction phase of EQMS: almost EQ equipment are not registered in DREAMS because the approach is not based on a standard data structure. In this study, we are to obtain the requirements of integrated EQMS by considering a standard and surveying the problems of current EQMS.

  8. A study on the implementation of an integrated Environmental Qualification Management System(EQMS) for nuclear power plant

    Bhang, Keug Jin; Jeong, Sun Chul; Kang, Pil Sun

    2012-01-01

    Environmental Qualification Management System(EQMS) for Nuclear Power Plant is a web based program for preventing degradation and managing original functions of environmental qualification equipment during nuclear power plant life cycle by inspecting and improving status of them periodically. But cognitive issues have stayed in the construction phase of EQMS: almost EQ equipment are not registered in DREAMS because the approach is not based on a standard data structure. In this study, we are to obtain the requirements of integrated EQMS by considering a standard and surveying the problems of current EQMS

  9. Study and discussion on management of nuclear island in-service inspection procedure system in nuclear power plant

    Zhang Xueliang; Fan Yancheng

    2014-01-01

    In-service inspection of nuclear island is the important way for keeping safety operation of nuclear power plant. Taking Daya Bay Nuclear Power Plant as example, the management problems of in-service inspection system was studied and discussed from the angle of references, contents, classifications etc. Based on comparison with French practice, some points of view on perfection of in-service inspection system and improvement of management ability under future multi-bases and multi-units management mode were presented. (authors)

  10. Economic evaluation of tokamak power plants

    Reid, R.L.; Steiner, D.

    1977-01-01

    This study reports the impact of plasma operating characteristics, engineering options, and technology on the capital cost trends of tokamak power plants. Tokamak power systems are compared to other advanced energy systems and found to be economically competitive. A three-phase strategy for demonstrating commercial feasibility of fusion power, based on a common-site multiple-unit concept, is presented

  11. Nuclear power plant operator licensing

    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.)

  12. Nuclear Power Plant Simulation Game.

    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)

  13. Human factors in nuclear power plants

    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)

  14. A Study on the Organizational Components Affecting the Communication-Related Events in Nuclear Power Plant

    Lee, Seung Min; Jang, In Seok; Seong, Poong Hyun

    2009-01-01

    It is important to communicate clearly and effectively in order to achieve and improve team performance, also in the view point of safety, in nuclear power plant (NPP). Researchers have studied on lots of accidents and incidents related to communication and analyzed the elements affecting communication fail in the side of sender-receiver communication process so that they have found which process was failed to communicate each other. But we cannot disregard on human cognition, level of understanding, and individual or team characteristic on the communication process, so we need to analyze the elements of communication-related events in the side of human and team components that we will find why operators could not avoid failing their communication. In this paper we enumerate key organizational components, collect events related to communication in NPP and count the total number of components affecting communication fail. Finally we perform the pairwise-comparison using those values and understand major factors affecting communication-related events

  15. Studies of the relationship between employee's safety consciousness, morale, and supervisor's leadership in nuclear power plant

    Misumi, Jyuji; Hiraki, Tadao; Sakurai, Yukihiro; Yoshida, Michio; Misumi, Emiko; Tokudome, Eiji.

    1996-01-01

    This study examined the relationship between employee's safety consciousness, morale, and supervisor's leadership using multiple regression analysis. Respondents were 2152 male employees who were working at nuclear power plants (operation division, maintenance division, and joint companies). Main results were as follows. (1) Individual morale variables, such as 'work motivation' and 'mental hygine', were correlated with leadership M behavior rather than with P behavior. On the other hand, group morale variables, such as 'teamwork' and 'meeting quality', were correlated with both P and M behavior. These results shows P and M leadership affect the employee's morale. (2) With regard to safety consciousness variables, 'communication' and 'work place norm' to ensure safety were strongly correlated to leadership both P and M behavior. However, neither 'sense of tension to ensure safety' nor 'experiencing cold shiver' were related to leadership P or M behavior. It was suggested that practices for accidents prevention in workplace are related to supervisor's P and M leadership behavior. (3) 'Sense of tension' to ensure safety and 'experiencing cold shiver' were negatively correlated with 'mental hygine', but positively correlated with 'work motivation'. These results suggest that increase of the work motivation might improve employee's awareness and ability for detecting human errors. (author)

  16. Studying radiolytic ageing of nuclear power plant electric cables with FTIR spectroscopy.

    Levet, A; Colombani, J; Duponchel, L

    2017-09-01

    Due to the willingness to extend the nuclear power plants length of life, it is of prime importance to understand long term ageing effect on all constitutive materials. For this purpose gamma-irradiation effects on insulation of instrumentation and control cables are studied. Mid-infrared spectroscopy and principal components analysis (PCA) were used to highlight molecular modifications induced by gamma-irradiation under oxidizing conditions. In order to be closer to real world conditions, a low dose rate of 11Gyh -1 was used to irradiate insulations in full cable or alone with a dose up to 58 kGy. Spectral differences according to irradiation dose were extracted using PCA. It was then possible to observe different behaviors of the insulation constitutive compounds i.e. ethylene vinyl acetate (EVA), ethylene propylene diene monomer (EPDM) and aluminium trihydrate (ATH). Irradiation of insulations led to the oxidation of their constitutive polymers and a modification of filler-polymer ratio. Moreover all these modifications were observed for insulations alone or in full cable indicating that oxygen easily diffuses into the material. Spectral contributions were discussed considering different degradation mechanisms. Copyright © 2017 Elsevier B.V. All rights reserved.

  17. Environment Quality: Impact From Traffic, Power Plant and Land Morphology, a Case Study of Prishtina

    Bajcinovci, Bujar

    2017-05-01

    Environmental air pollution is a global health concern, a complex phenomenon which is directly reflected on public health, economic and human development. Environmental air pollution has been drastically multiplied, followed by the beginning of the new Millennia in Prishtina, the capital city of the Kosovo. The new millennium began as a crucial activity for the city of Prishtina in terms of demographic, human geography, social and economic phenomena. The presented study aims to determine prevalent traffic and land morphology composition attributes, which have influenced and continue to have environmental impact in the city of Prishtina. According to the conceptual findings from the empirical observations, the heavy city traffic and the land morphology structure, determine the urban air pollution level. Prishtina is generally polluted due to its geomorphic position in relation to the power plants Kosovo A, and Kosova B. The impact of the above cited factors, is even bigger when the dominant winds prevail through valley, which encompasses the city. The findings from this paper propose the necessity of careful driven urban solutions.

  18. Environment Quality: Impact From Traffic, Power Plant and Land Morphology, a Case Study of Prishtina

    Bajcinovci Bujar

    2017-05-01

    Full Text Available Environmental air pollution is a global health concern, a complex phenomenon which is directly reflected on public health, economic and human development. Environmental air pollution has been drastically multiplied, followed by the beginning of the new Millennia in Prishtina, the capital city of the Kosovo. The new millennium began as a crucial activity for the city of Prishtina in terms of demographic, human geography, social and economic phenomena. The presented study aims to determine prevalent traffic and land morphology composition attributes, which have influenced and continue to have environmental impact in the city of Prishtina. According to the conceptual findings from the empirical observations, the heavy city traffic and the land morphology structure, determine the urban air pollution level. Prishtina is generally polluted due to its geomorphic position in relation to the power plants Kosovo A, and Kosova B. The impact of the above cited factors, is even bigger when the dominant winds prevail through valley, which encompasses the city. The findings from this paper propose the necessity of careful driven urban solutions.

  19. Sensitivity Study for Feed and Bleed Operation for Domestic CANDU Nuclear Power Plants

    Kim, K. S; Kim, B. S.; Yoo, H. K.; Kim, H. J. [Atomic Creative Technology Co., Daejeon (Korea, Republic of); Whang, S. W. [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2016-05-15

    The purpose of this paper is to evaluate the effects of the feed and bleed operation using DCT(Degassing Condenser Tank) over-pressure protection valves when LOCL4 with LOCL3 occurs during LPSD mid-loop operation. The CDF(Core Damage Frequency) of Level-1 Internal Event for Wolsong NPP Unit 1 during LPSD POS5A/5B accounts for about 89.08%(POS5A: 30.04%, POS5B: 59.04%) of the total CDF. For Wolsong NPP Unit 1 LPSD External Event, seismic analysis is excluded from this study because it is PSA-based SMA(Seismic Margin Assessment based Probabilistic Safety Assessment). For the domestic CANDU NPP, the feed and bleed operation using DCT over-pressure protection valves has been incorporated as an additional measure to mitigate the consequences during LPSD mid-loop operation. Since LOCL4 with LOCL3 is considered to be the event with highest frequency among all initial events, the effect of the feed and bleed operation on the safety of Nuclear Power Plant has been evaluated using PSA methodology.

  20. Elecnuc. Nuclear power plants worldwide

    1998-01-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)