Pre-fire planning for nuclear power plants

International Nuclear Information System (INIS)

Talbert, J.H.

1980-01-01

Regardless of the fire prevention measures which are taken, plant experience indicates that fires will occur in a nuclear power plant. When a fire occurs, the plant staff must handle the fire emergency. Pre-fire planning is a method of developing detailed fire attack plans and salvage operations to protect equipment from damage due to fire and fire fighting operations. This paper describes the purpose and use of a pre-fire plan to achieve these goals in nuclear power plants

Fuzzy logic control of nuclear power plant

International Nuclear Information System (INIS)

Yao Liangzhong; Guo Renjun; Ma Changwen

1996-01-01

The main advantage of the fuzzy logic control is that the method does not require a detailed mathematical model of the object to be controlled. In this paper, the shortcomings and limitations of the model-based method in nuclear power plant control were presented, the theory of the fuzzy logic control was briefly introduced, and the applications of the fuzzy logic control technology in nuclear power plant controls were surveyed. Finally, the problems to be solved by using the fuzzy logic control in nuclear power plants were discussed

Slovenske elektrarne, a.s., Enterprise Vojany power plant

International Nuclear Information System (INIS)

2005-01-01

This brochure describes the Enterprise Vojany power plant (SE-EVO) is described. This is brown coal burning ((EVO II) and natural gas or fuel oil burning (EVO I) power plant. Technical data in detail of SE-EVO as well as results of up-grade of the SE-EVO are presented

Fusion power core engineering for the ARIES-ST power plant

International Nuclear Information System (INIS)

Tillack, M.S.; Wang, X.R.; Pulsifer, J.; Malang, S.; Sze, D.K.; Billone, M.; Sviatoslavsky, I.

2003-01-01

ARIES-ST is a 1000 MWe fusion power plant based on a low aspect ratio 'spherical torus' (ST) plasma. The ARIES-ST power core was designed to accommodate the unique features of an ST power plant, to meet the top-level requirements of an attractive fusion energy source, and to minimize extrapolation from the fusion technology database under development throughout the world. The result is an advanced helium-cooled ferritic steel blanket with flowing PbLi breeder and tungsten plasma-interactive components. Design improvements, such as the use of SiC inserts in the blanket to extend the outlet coolant temperature range were explored and the results are reported here. In the final design point, the power and particle loads found in ARIES-ST are relatively similar to other advanced tokamak power plants (e.g. ARIES-RS [Fusion Eng. Des. 38 (1997) 3; Fusion Eng. Des. 38 (1997) 87]) such that exotic technologies were not required in order to satisfy all of the design criteria. Najmabadi and the ARIES Team [Fusion Eng. Des. (this issue)] provide an overview of ARIES-ST design. In this article, the details of the power core design are presented together with analysis of the thermal-hydraulic, thermomechanical and materials behavior of in-vessel components. Detailed engineering analysis of ARIES-ST TF and PF systems, nuclear analysis, and safety are given in the companion papers

Nuclear Power Station Kalkar, 300 MWe Prototype Nuclear Power Plant with Fast Sodium Cooled Reactor (SNR-300), Plant description

International Nuclear Information System (INIS)

1984-06-01

The nuclear power station Kalkar (SNR-300) is a prototype with a sodium cooled fast reactor and a thermal power of 762 MW. The present plant description has been made available in parallel to the licensing procedure for the reactor plant and its core Mark-Ia as supplementary information for the public. The report gives a detailed description of the whole plant including the prevention measures against the impact of external and plant internal events. The radioactive materials within the reactor cooling system and the irradiation protection and surveillance measures are outlined. Finally, the operation of the plant is described with the start-up procedures, power operation, shutdown phases with decay heat removal and handling procedures

Advantages of butterfly valves for power plants

International Nuclear Information System (INIS)

Lapadat, J.T.

1977-01-01

Butterfly valves are increasingly used in nuclear power plants. They are used in CANDU reactors for class 2 and 3 service, to provide emergency and tight shutoff valves for all inlets and outlets of heat exchangers and all calandria penetrations. Guidelines for meeting nuclear power plant valve specifications are set out in ASME Section 3, Nuclear Power Plant Components. Some details of materials of construction, type of actuator, etc., for various classes of nuclear service are tabulated in the present article. The 'fishtail' butterfly valve is an improved design with reduced drag, as is illustrated and explained. (N.D.H.)

Docommissioning of nuclear power plants

International Nuclear Information System (INIS)

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)

Fitting of power generated by nuclear power plants into the Hungarian electricity system

International Nuclear Information System (INIS)

Lengyel, Gyula; Potecz, Bela

1984-01-01

The moderate increase of electrical energy demands (3% at present) can only be met by the parallel application of fossil and nuclear power plants and by electric power import via the transmission lines of the CMEA countries. The changes in the electrical energy and fuel demands and the development of the available capacities during the last 35 years are reviewed. The major purpose of Hungarian power economy is to save hydrocarbon fuels by taking advantages of power import opportunities by operating nuclear power plants at maximum capacity and the coal fired power stations at high capacity. The basic principles, the algorithm applied to optimize the load distribution of the electrical power system are discussed in detail with special attention to the role of nuclear power. The planned availability of nuclear power plants and the amount of electricity generated by nuclear plants should also be optimized. (V.N.)

Multi-variable systems in nuclear power plant

International Nuclear Information System (INIS)

Collins, G.B.; Howell, J.

1982-01-01

Nuclear power plant are complex multi-variable dynamically interactive systems which employ many facets of systems and control theory in their analysis and design. Whole plant mathematical models must be developed and validated and in addition to their obvious role in control system synthesis and design, they are also widely used for operational constraint and plant malfunction analysis. The need for and scope of an integrated power plant control system is discussed and, as a specific example, the design of an integrated feedwater regulator is reviewed. The multi-variable frequency response analysis employed in the design is described in detail. (author)

Site survey for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

Nuclear power plant analyzer

International Nuclear Information System (INIS)

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)

Vulnerability of the nuclear power plant in war conditions

International Nuclear Information System (INIS)

Stritar, A.; Mavko, B.

1992-01-01

In the summer 1991 the Nuclear Power Plant Krsko in Slovenia found itself in the area of military operations. This way probably the first commercial nuclear power plant, to which it was threatened with the air jet attack. A number of never before asked questions had to be answered by the operating staff and supporting organizations. In this paper some aspects of the nuclear power plant safety in war condition are described: the selection of the best plant operating state before the attack and the determination of plant system vulnerability. It was concluded, that the best operating mode, into which the plant should be brought before the attack, is the cold shutdown mode. The problem of Nuclear Power Plant safety in war conditions should be addressed in more detail in the future. (author) [sl

Thermal power plants and environment

International Nuclear Information System (INIS)

1997-01-01

Recent versions of the air quality models which are reviewed and approved from the Environmental Protection Agency (EPA) are analysed in favour of their application in simple and complex terrain, different meteorological conditions and modifications in the sources of pollutant emissions. Improvement of the standard methods for analysis of the risks affecting the environment from different energy sources has been carried out. The application of the newly introduced model enabled (lead to performing) risk analysis of the coal power plants compared to other types of energy sources. Detailed investigation of the risk assessment and perception from coal power plants, has been performed and applied to the Macedonian coal power plants. Introducing the concept of 'psychological pollution', a modification of the standard models and programs for risk assessment from various energy sources has been suggested (proposed). The model has been applied to REK Bitola, where statistically relevant differences in relation to the control groups have been obtained. (Original)

Economic analysis of power generation from floating solar chimney power plant

International Nuclear Information System (INIS)

Zhou, Xinping; Yang, Jiakuan; Xiao, Bo; Wang, Fen

2009-01-01

Solar chimney thermal power technology that has a long life span is a promising large-scale solar power generating technology. This paper performs economic analysis of power generation from floating solar chimney power plant (FSCPP) by analyzing cash flows during the whole service period of a 100 MW plant. Cash flows are influenced by many factors including investment, operation and maintenance cost, life span, payback period, inflation rate, minimum attractive rate of return, non-returnable subsidy rate, interest rate of loans, sale price of electricity, income tax rate and whether additional revenue generated by carbon credits is included or not. Financial incentives and additional revenue generated by carbon credits can accelerate the development of the FSCPP. Sensitivity analysis to examine the effects of the factors on cash flows of a 100 MW FSCPP is performed in detail. The results show that the minimum price for obtaining minimum attractive rate of return (MARR) of 8% reaches 0.83 yuan (kWh) -1 under financial incentives including loans at a low interest rate of 2% and free income tax. Comparisons of economics of the FSCPP and reinforced concrete solar chimney power plant or solar photovoltaic plant are also performed by analyzing their cash flows. It is concluded that FSCPP is in reality more economical than reinforced concrete solar chimney power plant (RCSCPP) or solar photovoltaic plant (SPVP) with the same power capacity. (author)

Emergency power systems at nuclear power plants

International Nuclear Information System (INIS)

1991-01-01

This Safety Guide was prepared as part of the Nuclear Safety Standards programme for establishing Codes and Safety Guides relating to nuclear power plants (NPPs). The first edition of the present Safety Guide was developed in the early 1980s. The text has now been brought up-to-date, refined in several details and amended to include non-electrical diverse and independent power sources. This Guide applies to NPP for which the total power supply comprises a normal power supply and an emergency power supply (EPS), which may be electrical or a combination of electrical and non-electrical. The Guide provides general guidance for all types of EPS and specific guidance on the design safety requirements and the features of the electrical and non-electrical portions of the EPS. 9 figs, 2 tabs

Construction of the Temelin nuclear power plant

International Nuclear Information System (INIS)

Jicha, J.

1989-01-01

The Temelin nuclear power plant with four WWER-1000 reactors is designed to supply electricity in an amount of 23 TWh/yr and heat in an amount of 8000 TJ/yr in the first stage. The maximum heat extraction should be 922 MW. The plant construction includes the building of 10 buildings, the total cost being 52 thousand million Czechoslovak crowns. Another 41 investment items are associated with the plant construction. The most important of them include constructions for leading out the electric power, for standby electricity supply for the power plant, and for the extraction of heat from the plant and its supply to the town of Ceske Budejovice. The first unit should be started up for test performance in November 1992, the second in 1994 and the whole power plant should be complete by 1998. The state of the construction by February 1989 is described in detail. Attention is also paid to the preparatory activity for the operation and to social welfare of the personnel. (Z.M.)

Radioactive commitment due to use of coal in power plants

International Nuclear Information System (INIS)

Fenger, J. and H. Flyger.

1980-11-01

A short review of the literature on release of radioactivity due to use of coal in power plants with the emphasis on the stack effluent and waste products. It is concluded that during normal operation coal fired power plants give a larger dose commitment than nuclear power plants, but both types have insignificant effects. The problem of waste management has never been studied in detail; ash deposit should probably be monitored. (Auth)

Review of nuclear power plant systems

International Nuclear Information System (INIS)

Doehler

1980-01-01

This presentation starts with a brief description of the Technischer Ueberwachungs-Verein (TUeV) and its main activities in the field of technical assessments. The TUeV-organisation is in general the assessor who performs the review if nuclear power plant systems, structures and equipment. All aspects relating to the safe operation of nuclear power plants are assessed by the TUeV. This paper stresses the review of the design of nuclear power plant systems and structures. It gives an outline on the procedure of an assessment, starting with the regulatory requirements, going into the papers of the applicant and finally ending with the TUeV-appraisal. This procedure is shown using settlement measuring requirements as an example. The review of the design of mechanical structures such as pipes, valves, pump and vessels is shown in detail. (RW)

World nuclear power plant capacity

International Nuclear Information System (INIS)

1991-01-01

This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA) [de

Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.; Edwards, R.M.; Ray, A.; Lee, K.Y.; Garcia, H.E.: Chavez, C.M.; Turso, J.A.; BenAbdennour, A.

1991-01-01

In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Second Annual Technical Progress report covers the period from September 1990 to September 1991. It summarizes the second year accomplishments while the appendices provide detailed information presented at conference meetings. These are two primary goals of this research. The first is to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz, a project consultant during the first year of the project. This philosophy, as presented in the first annual technical progress report, is to improve public perception of the safety of nuclear power plants by incorporating a high degree automation where greatly simplified operator control console minimizes the possibility of human error in power plant operations. A hierarchically distributed control system with automated responses to plant upset conditions is the focus of our research to achieve this goal. The second goal is to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-II steam plant

Guideline on dependability management for the power industry: detailed description of international power plant equipment dependability indicators

International Nuclear Information System (INIS)

Procaccia, H.; Silberberg, S.

1997-01-01

Dependability Management involves the management of reliability, availability maintainability and maintenance support, and in the power industry is necessary to ensure that plant meets the Reliability, Availability and Maintainability (RAM) targets set by the Utilities. In 1993, a joint Standard on Dependability Programme Management - Part 1: Dependability Programme Management), ISO 9000-': 1993 (Quality Management and Quality Assurance Standards - Part 4: Guide to Dependability Programme Management). UNIPEDE established a group of experts (Nulethermaint) to produce guidelines on its implementation specifically for use in the power industry. The present document comprises Part 2 OF THE UNIPEDE plant performance indicators and can be applied to both nuclear and fossil plant. There are five different equipment dependability indicators, all relating to equipment maintenance activities and the impact that these activities have on the loss of both system function and unit capability. Per year, each of the indicators can be applied separately to both preventive maintenance and corrective maintenance, giving rise to as many as ten indicator values for each item of equipment. Used in this way, the indicators provide a comprehensive picture of the maintenance strategy employed for key pieces of equipment, and its effectiveness. They are, therefore, a valuable managerial tool for improving maintenance activities at the unit level within a utility. This document provides guidance on the division of both nuclear and fossil power plant into their component parts and in each case the types of equipment having the most dominant effect on dependability are identified. These are the items which merit the greatest attention with regard to the equipment dependability indicators. (authors)

Economics of hybrid photovoltaic power plants

Energy Technology Data Exchange (ETDEWEB)

Breyer, Christian

2012-08-16

plants, wind power, solar thermal power (STEG) and hydro power plants. For the 2010s, detailed global demand curves are derived for hybrid PV-Fossil power plants on a per power plant, per country and per fuel type basis. The fundamental technical and economic potentials for hybrid PV-STEG, hybrid PV-Wind and hybrid PV-Hydro power plants are considered. The global resource availability for PV and wind power plants is excellent, thus knowing the competitive or complementary characteristic of hybrid PV-Wind power plants on a local basis is identified as being of utmost relevance. The complementarity of hybrid PV-Wind power plants is confirmed. As a result of that almost no reduction of the global economic PV market potential need to be expected and more complex power system designs on basis of hybrid PV-Wind power plants are feasible. The final target of implementing renewable power technologies into the global power system is a nearly 100% renewable power supply. Besides balancing facilities, storage options are needed, in particular for seasonal power storage. Renewable power methane (RPM) offers respective options. A comprehensive global and local analysis is performed for analysing a hybrid PV-Wind-RPM combined cycle gas turbine power system. Such a power system design might be competitive and could offer solutions for nearly all current energy system constraints including the heating and transportation sector and even the chemical industry. Summing up, hybrid PV power plants become very attractive and PV power systems will very likely evolve together with wind power to the major and final source of energy for mankind.

Economics of hybrid photovoltaic power plants

Energy Technology Data Exchange (ETDEWEB)

Breyer, Christian

2012-08-16

coal fired power plants, wind power, solar thermal power (STEG) and hydro power plants. For the 2010s, detailed global demand curves are derived for hybrid PV-Fossil power plants on a per power plant, per country and per fuel type basis. The fundamental technical and economic potentials for hybrid PV-STEG, hybrid PV-Wind and hybrid PV-Hydro power plants are considered. The global resource availability for PV and wind power plants is excellent, thus knowing the competitive or complementary characteristic of hybrid PV-Wind power plants on a local basis is identified as being of utmost relevance. The complementarity of hybrid PV-Wind power plants is confirmed. As a result of that almost no reduction of the global economic PV market potential need to be expected and more complex power system designs on basis of hybrid PV-Wind power plants are feasible. The final target of implementing renewable power technologies into the global power system is a nearly 100% renewable power supply. Besides balancing facilities, storage options are needed, in particular for seasonal power storage. Renewable power methane (RPM) offers respective options. A comprehensive global and local analysis is performed for analysing a hybrid PV-Wind-RPM combined cycle gas turbine power system. Such a power system design might be competitive and could offer solutions for nearly all current energy system constraints including the heating and transportation sector and even the chemical industry. Summing up, hybrid PV power plants become very attractive and PV power systems will very likely evolve together with wind power to the major and final source of energy for mankind.

Nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

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

Steam turbines for nuclear power plants

International Nuclear Information System (INIS)

Kosyak, Yu.F.

1978-01-01

Considered are the peculiarities of the design and operation of steam turbines, condensers and supplementary equipment of steam turbines for nuclear power plants; described are the processes of steam flow in humid-steam turbines, calculation and selection principles of main parameters of heat lines. Designs of the turbines installed at the Charkov turbine plant are described in detail as well as of those developed by leading foreign turbobuilding firms

Impact of Wind Power Plants on Voltage Control of Power System

DEFF Research Database (Denmark)

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

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

LNG plant combined with power plant

Energy Technology Data Exchange (ETDEWEB)

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

1997-06-01

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

LNG plant combined with power plant

International Nuclear Information System (INIS)

Aoki, I.; Kikkawa, Y.

1997-01-01

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

Influence of Egyptian electrical grid and nuclear power plants under disturbances based on PSS/E

International Nuclear Information System (INIS)

Shaat, M. K.; Kotb, S. A.; Mahmoud, H. M.

2012-12-01

The capacity of the electrical power system in Egypt will increase rapidly in the coming twenty years. In year 2018, power generation will be connecting to the Egyptian electrical grid. Consequently, the interaction of nuclear power plants and other systems become a very important issue, and a detailed nuclear power model for the medium-term and long-term power system stability should be developed. However, there is no nuclear unit model that can describe the detailed characteristics of the nuclear unit in the available commercial power system simulation software. In this paper, a detailed pressurized water reactor (PWR) nuclear unit model for medium-term and long-term power system transient stability is proposed. The model is implemented by a user defined program in PSS/E through PSS/E Mat lab Seamanlike interface. Also this paper proposes a design of power plant rector controller for the nuclear power plant. This model can be used to analyze the difference influences between the Egyptian electrical grid and nuclear power plants for examples transient fault on electrical grid and outage of nuclear power plant. The simulation results show that the proposed model is valid. (Author)

Survey of strong motion earthquake effects on thermal power plants in California with emphasis on piping systems. Volume 2, Appendices

International Nuclear Information System (INIS)

Stevenson, J.D.

1995-11-01

Volume 2 of the ''Survey of Strong Motion Earthquake Effects on Thermal Power Plants in California with Emphasis on Piping Systems'' contains Appendices which detail the detail design and seismic response of several power plants subjected to strong motion earthquakes. The particular plants considered include the Ormond Beach, Long Beach and Seal Beach, Burbank, El Centro, Glendale, Humboldt Bay, Kem Valley, Pasadena and Valley power plants. Included is a typical power plant piping specification and photographs of typical power plant piping specification and photographs of typical piping and support installations for the plants surveyed. Detailed piping support spacing data are also included

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

Energy Technology Data Exchange (ETDEWEB)

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.

Maryland power plants and the environment: A review of the impacts of power plants and transmission lines on Maryland's natural resources. Biannually report

International Nuclear Information System (INIS)

1993-03-01

The report, published biannually by Maryland's Power Plant Research Program, is a summary of current information related to environmental impacts associated with electric power generation in Maryland. Topics discussed in detail include: Power Supply and Demand; Air Quality; Surface and Groundwater Impacts; Terrestrial Impacts; Radiological Impacts; and Acid Deposition

Human Factors Engineering Incorporated into the Carolina Power and Light company's nuclear power plant control panel modifications

International Nuclear Information System (INIS)

Beith, D.M.; Shoemaker, E.M.; Horn, K.; Boush, D.

1988-01-01

Maintaining human factors conventions/practices that were established during the Detailed Control Design Review (DCRDR), is difficult if Human Factors Engineering (HFE) is not incorporated into the plant modification process. This paper presents the approach used at Carolina Power and Light's nuclear power plants that has successfully incorporated human factors engineering into their plant modification process. An HFE Design Guide or HFE Specification was developed which is used by the design engineers or plant engineering support groups in the preparation of plant modifications

Nuclear power plant emergency preparedness

International Nuclear Information System (INIS)

2005-01-01

The guide sets forth detailed requirements on how the licensee of a nuclear power plant shall plan, implement and maintain emergency response arrangements. The guide is also applied to nuclear material and nuclear waste transport in situations referred to in guide YVL 6.5. Requirements on physical protection are presented in a separate guide of Finnish Radiation and Nuclear Safety Authority (STUK)

Fusion power plant studies in Europe

International Nuclear Information System (INIS)

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

What about improving the productivity of electric power plants

International Nuclear Information System (INIS)

Lawroski, H.; Knecht, P.D.; Prideaux, D.L.; Zahner, R.R.

1976-01-01

The FEA in April of 1974 established an Interagency Task Group on Power Plant Reliability, which was charged with the broad objective of improving the productivity of existing and planned large fossil-fueled and nuclear power plants. It took approximately 11 months for the task force to publish a report, ''Report on Improving the Productivity of Electrical Power Plants'' (FEA-263-G), a detailed analysis and comparison of successful and below-average-performance power plants. The Nuclear Service Corp. portion of this study examined four large central-station power plants: two fossil (coal) and two nuclear plants. Only plants with electrical generation capacities greater than 400 MWe were considered. The study included the following: staff technical skill, engineering support, QA program, plant/corporate coordination, operation philosophy, maintenance programs, federal/state regulations, network control, and equipment problems. Personnel were interviewed, and checklists providing input from some 21 or more plant and corporate personnel of each utility were utilized. Reports and other documentation were also reviewed. It was recognized early that productivity is closely allied to technical skills and positive motivation. For this reason, considerable attention was given to people in this study

A selection of problems related to safe working conditions in nuclear power plants

International Nuclear Information System (INIS)

Brunner, K.H.

1984-01-01

Two representative examples were chosen to demonstrate that the problems related to safe working conditions can be solved with work being prepared extensively and in detail taking into consideration radiation protection and conventional job safety measures and with qualified staff. Most of the job safety problems in nuclear power plants are pretty much the same as in conventional plants. Despite successful implementation of employment and radiation protection in nuclear power plants, improvements in detail are possible and make sense. (orig.) [de

Are atomic power plants saver than nuclear power plants

International Nuclear Information System (INIS)

Roeglin, H.C.

1977-01-01

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

700 C power plant technology. Status and challenge

Energy Technology Data Exchange (ETDEWEB)

Tschaffon, Helmut [E.ON Energie AG, Muenchen (Germany)

2010-07-01

Coal will remain an indispensable major source of energy for power generation in the world in the coming decades, because there are resources for hundreds of years. Coal fired power plants can be operated very flexible which gets increasing importance due to the stochastic input from regenerative energies like wind and solar energy. Sustainable technologies for cool-fired power plants have to be developed to optimise environmental protection and to save valuable resources and reduce CO{sub 2}-emissions. Future coal fired steam power plants aim an elevated steam temperature of about 700 C to reach a net efficiency of about 50%. This paper will give an overview over the status of the development of the 700 C technology and will highlight the challenges to be overcome before their commercial use. The European way to a 700 C Power plant started with the project AD700 in the year 1998. In this project the basic design of a 400 MW demo plant was done and some material tests and component qualifications for nickel-based alloys and new austenitic steels were started and terminated. AD700 delivered the basis of the design of the Component Test Facility COMTES700 (RFCS funded project with European manufacturers and utilities). COMTES 700 was operated between 2005 and 2009. It was integrated into the E.ON power plant Scholven in Germany to test mainly nickel based materials and power plant components. In the project NRWPP700 (2006-2010, funded by NRW and financed by European utilities) the detail design of the steam generator, piping system and turbine of a 500 MW power plant was done. In 7 material projects the qualification of components and materials was supported. At the same time of lot of national and international R and D projects (e.g. MARCKO and COORETEC) were performed. Due to the high amount of these projects they cannot be mentioned here in a detailed way. In 2007 the E.ON project 50plus was started. The aim was to plan and build a 700 C demo plant in

Multilevel flow modeling of Monju Nuclear Power Plant

DEFF Research Database (Denmark)

Lind, Morten; Yoshikawa, Hidekazu; Jørgensen, Sten Bay

2011-01-01

Multilevel Flow Modeling is a method for modeling complex processes on multiple levels of means-end and part-whole abstraction. The modeling method has been applied on a wide range of processes including power plants, chemical engineering plants and power systems. The modeling method is supported...... with reasoning tools for fault diagnosis and control and is proposed to be used as a central knowledge base giving integrated support in diagnosis and maintenance tasks. Recent developments of MFM include the introduction of concepts for representation of control functions and the relations between plant...... functions and structure. The paper will describe how MFM can be used to represent the goals and functions of the Japanese Monju Nuclear Power Plant. A detailed explanation will be given of the model describing the relations between levels of goal, function and structural. Furthermore, it will be explained...

Fighting and preventing post-earthquake fires in nuclear power plant

International Nuclear Information System (INIS)

Lu Xuefeng; Zhang Xin

2011-01-01

Nuclear power plant post-earthquake fires will cause not only personnel injury, severe economic loss, but also serious environmental pollution. For the moment, nuclear power is in a position of rapid development in China. Considering the earthquake-prone characteristics of our country, it is of great engineering importance to investigate the nuclear power plant post-earthquake fires. This article analyzes the cause, influential factors and development characteristics of nuclear power plant post-earthquake fires in details, and summarizes the three principles should be followed in fighting and preventing nuclear power plant post-earthquake fires, such as solving problems in order of importance and urgency, isolation prior to prevention, immediate repair and regular patrol. Three aspects were pointed out that should be paid attention in fighting and preventing post-earthquake fires. (authors)

Preliminary project concerning the straw-based combined power-heat plant at Glamsbjerg

International Nuclear Information System (INIS)

Gabriel, S.; Koch, T.

1994-01-01

The supplement to the main report on the planned dual-purpose power plant at Glamsbjerg contains documentation of the straw gasification and pyrolysis process, a detailed description of the power plant components, and the procedures of operation and maintenance of the combined systems. (EG)

Nuclear Power Plant 1996

International Nuclear Information System (INIS)

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)

CEZ utility's coal-fired power plants: towards a higher environmental friendliness

International Nuclear Information System (INIS)

Kindl, V.; Spilkova, T.; Vanousek, I.; Stehlik, J.

1996-01-01

Environmental efforts of the major Czech utility, CEZ a.s., are aimed at reducing air pollution arising from electricity and heat generating facilities. There are 3 main kinds of activity in this respect: phasing out of coal fired power plants; technological provisions to reduce emissions of particulate matter, sulfur dioxide, and nitrogen oxides from those coal fired units that are to remain in operation after 1998; and completion of the Temelin nuclear power plant. In 1995, emissions of particulate matter, sulfur dioxide, nitrogen oxides, and carbon monoxide from CEZ's coal fired power plants were 19%, 79%, 59%, and 60%, respectively, with respect to the situation in 1992. The break-down of electricity generation by CEZ facilities (in GWh) was as follows in 1995: hydroelectric power plants 1673, nuclear power plants 12230, coal fired power plants without desulfurization equipment 30181, and coal fired power plants with desulfurization equipment 2277. Provisions implemented to improve the environmental friendliness of the individual CEZ's coal fired power plants are described in detail. (P.A.). 5 tabs., 1 fig

Employing modern power plant simulators in nuclear power plants

International Nuclear Information System (INIS)

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.)

Seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Senne Junior, M.

1983-07-01

A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those plants, against the action of earth quarks is described. The instrumentation is based on the nuclear standards and other components used, as well as their general localization is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The accelerometer is described in detail. (Author) [pt

Nuclear power plants and environment

International Nuclear Information System (INIS)

Agudo, E.G.; Penteado Filho, A.C.

1980-01-01

The question of nuclear power plants is analysed in details. The fundamental principles of reactors are described as well as the problems of safety involved with the reactor operation and the quantity and type of radioactive released to the environment. It shows that the amount of radioactive is very long. The reactor accidents has occurred, as three mile island, are also analysed. (M.I.A.)

Safety classification of nuclear power plant systems, structures and components

International Nuclear Information System (INIS)

1992-01-01

The Safety Classification principles used for the systems, structures and components of a nuclear power plant are detailed in the guide. For classification, the nuclear power plant is divided into structural and operational units called systems. Every structure and component under control is included into some system. The Safety Classes are 1, 2 and 3 and the Class EYT (non-nuclear). Instructions how to assign each system, structure and component to an appropriate safety class are given in the guide. The guide applies to new nuclear power plants and to the safety classification of systems, structures and components designed for the refitting of old nuclear power plants. The classification principles and procedures applying to the classification document are also given

Operator psychological selection system for nuclear power plant

International Nuclear Information System (INIS)

He Xuhong; Huang Xiangrui

2004-01-01

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

Advanced design nuclear power plants: Competitive, economical electricity. An analysis of the cost of electricity from coal, gas and nuclear power plants

International Nuclear Information System (INIS)

1992-06-01

This report presents an updated analysis of the projected cost of electricity from new baseload power plants beginning operation around the year 2000. Included in the study are: (1) advanced-design, standardized nuclear power plants; (2) low emissions coal-fired power plants; (3) gasified coal-fired power plants; and (4) natural gas-fired power plants. This analysis shows that electricity from advanced-design, standardized nuclear power plants will be economically competitive with all other baseload electric generating system alternatives. This does not mean that any one source of electric power is always preferable to another. Rather, what this analysis indicates is that, as utilities and others begin planning for future baseload power plants, advanced-design nuclear plants should be considered an economically viable option to be included in their detailed studies of alternatives. Even with aggressive and successful conservation, efficiency and demand-side management programs, some new baseload electric supply will be needed during the 1990s and into the future. The baseload generating plants required in the 1990s are currently being designed and constructed. For those required shortly after 2000, the planning and alternatives assessment process must start now. It takes up to ten years to plan, design, license and construct a new coal-fired or nuclear fueled baseload electric generating plant and about six years for a natural gas-fired plant. This study indicates that for 600-megawatt blocks of capacity, advanced-design nuclear plants could supply electricity at an average of 4.5 cents per kilowatt-hour versus 4.8 cents per kilowatt-hour for an advanced pulverized-coal plant, 5.0 cents per kilowatt-hour for a gasified-coal combined cycle plant, and 4.3 cents per kilowatt-hour for a gas-fired combined cycle combustion turbine plant

Radiation protection during operation of nuclear power plants

International Nuclear Information System (INIS)

1983-01-01

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

Ground acceleration in a nuclear power plant

International Nuclear Information System (INIS)

Pena G, P.; Balcazar, M.; Vega R, E.

2015-09-01

A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

Some aspects of nuclear power plant safety under war conditions

International Nuclear Information System (INIS)

Stritar, A.; Mavko, B.; Susnik, J.; Sarler, B.

1993-01-01

In the summer of 1991, the Krsko nuclear power plant in Slovenia found itself in an area of military operations. This was probably the first commercial nuclear power plant to have been threatened by an attack by fighter jets. A number of never-before-asked questions had to be answered by the operating staff and supporting organizations. Some aspects of nuclear power plant safety under war conditions are described, such as the selection of the best plant operating state before the attack and the determination of plant system vulnerability and dose releases from the potentially damaged spent fuel in the spent-fuel pit. The best operating mode to which the plant should be brought before the attack is cold shutdown, and radiological consequences to the environment after the spent fuel is damaged and the water in the pit is lost are not very high. The problem of nuclear power plant safety under war conditions should be addressed in more detail in the future

Kansas Power Plants

Data.gov (United States)

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

Plant operational states analysis in low power and shutdown PSA

International Nuclear Information System (INIS)

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

2013-01-01

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

Directory of nuclear power plants in the world, 1985

International Nuclear Information System (INIS)

Fujii, Haruo

1985-01-01

This book presents technical information and estimates trends of load factors and construction costs of nuclear power plants. Particularly road maps indicating plants are drawn in, which would be practical in visiting them. The data used here are directly confirmed by operators in every part of the world. Therefore, they reflect up-to-date nuclear power developments and its future. This allows wide and exact understanding of world's nuclear power. Chapter 1 presents nuclear power growth around the world and estimates forecasts based on information from electric power companies: nuclear power growths and the growths in the number of reactors around the world, in WOCA (World outside the Centrally Planned Economies Area), in CPEA (Centrally Planned Economies Area) are analyzed in detail. Chapter 2 presents nuclear power plants on maps by country. The maps show exact locations of nuclear power plants with local cities around them, rivers and lakes. For convenience, symbols are given to aid in identifying the types of reactors. Chapter 3 presents general information of nuclear power plants. Also the addresses of operators, all segments of nuclear power supply industries and nuclear organizations are included. For convenience, the index of nuclear power plants is added. Chapter 4 presents technical information, road maps in large scales and photographs of nuclear power plants in the world. The road maps show exact locations of plants. Chapter 5 presents operating experiences, load factors, refuelling and maintenance outages. The trends of data are analyzed both regionally (WOCA, CPEA) and world-widely. Chapter 6 presents trends of construction costs, component costs as percent of total construction costs and direct costs, and construction durations. (J.P.N.)

Comparative studies between nuclear power plants and hydroelectric power plants

International Nuclear Information System (INIS)

Menegassi, J.

1984-01-01

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

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

International Nuclear Information System (INIS)

Ichiki, Tadaharu; Tanaka, Masayuki.

1991-01-01

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

Wind Power Plant Control Optimisation with Incorporation of Wind Turbines and STATCOMs

DEFF Research Database (Denmark)

Petersen, Lennart; Kryezi, Fitim; Iov, Florin

2015-01-01

This paper addresses a detailed design and tuning of a wind power plant slope voltage control with reactive power contribution of wind turbines and STATCOMS. First, small-signal models of a single wind turbine and the whole wind power plant are developed, being appropriate for voltage control...... assessment. An exemplary wind power plant located in the United Kingdom and the corresponding grid code requirements are used as a base case. The final design and tuning process of the voltage controller results in a guidance, proposed for this particular control architecture. It provides qualitative...... outcomes regarding the impact of system delays, grid conditions and various operating conditions of the wind power plant, with and without incorporation of STATCOMS....

Human error: An essential problem of nuclear power plants

International Nuclear Information System (INIS)

Smidt, D.

1981-01-01

The author first defines the part played by man in the nuclear power plant and then deals in more detail with the structure of his valse behavior in tactical and strategic repect. The dicussion of tactical errors and their avoidance is follwed by a report on the actual state of plant technology and possible improvements. Subsequently a study of the strategic errors including the conclusion to be drawn until now (joint between plant and man, personal selection and education) is made. If the joints between man and machine are designed according and physiological strenghts and weaknesses of man are fully realized and taken into account human errors not be essential problem in nuclear power plant. (GL) [de

Computer-based control systems of nuclear power plants

International Nuclear Information System (INIS)

Kalashnikov, V.K.; Shugam, R.A.; Ol'shevsky, Yu.N.

1975-01-01

Computer-based control systems of nuclear power plants may be classified into those using computers for data acquisition only, those using computers for data acquisition and data processing, and those using computers for process control. In the present paper a brief review is given of the functions the systems above mentioned perform, their applications in different nuclear power plants, and some of their characteristics. The trend towards hierarchic systems using control computers with reserves already becomes clear when consideration is made of the control systems applied in the Canadian nuclear power plants that pertain to the first ones equipped with process computers. The control system being now under development for the large Soviet reactors of WWER type will also be based on the use of control computers. That part of the system concerned with controlling the reactor assembly is described in detail

Calibration of radiation monitors at nuclear power plants

International Nuclear Information System (INIS)

Boudreau, L.; Miller, A.D.; Naughton, M.D.

1994-03-01

This work was performed to provide guidance to the utilities in the primary and secondary calibration of the radiation monitoring systems (RMS) installed in nuclear power plants. These systems are installed in nuclear power plants to monitor ongoing processes, identify changing radiation fields, predict and limit personnel radiation exposures and measure and control discharge of radioactive materials to the environment. RMS are checked and calibrated on a continuing basis to ensure their precision and accuracy. This report discusses various approaches towards primary and secondary calibrations of the RMS equipment in light of accepted practices at typical power plants and recent interpretations of regulatory guidance. Detailed calibration techniques and overall system responses, trends, and practices are discussed. Industry, utility, and regulatory sources were contacted to create an overall consensus of the most reasonable approaches to optimizing the performance of this equipment

Power plant cable condition monitoring and testing at Georgia Power

International Nuclear Information System (INIS)

Champion, T.C.

1988-01-01

Georgia Power's Research Center has been heavily involved in the evaluation of electrical insulating materials and cables since its inception more than 17 years ago. For the past ten years that expertise has been applied to cables used in generation plants. This paper discusses the results of two test programs. The first is a quality control inspection on 169 samples of new power generation cables. The second is a material degradation evaluation on four short cable samples removed from a coal fired plant during an equipment upgrade. The new material evaluation was performed to identify the cause of a high failure rate upon initial hi-pot testing of newly installed cables. The material degradation evaluation was performed to evaluate the need for replacement of existing cables during an equipment upgrade. Results of the evaluations have led to development of a detailed proposal for a program to evaluate cable degradation and remaining life for cables used in power generation facilities

Presenting a model of repair and preventing maintenance of Bushehr nuclear power plants analyzing the data of similar nuclear power plants

International Nuclear Information System (INIS)

Parikhan, Hammidreza

1997-01-01

Due to the increase application of nuclear energy for producing electricity, special attention must be paid to their maintenance activities in general and preventive maintenance in particular. It has been shown that a well established preventive maintenance programme will enhance the reliability and availability of nuclear power plants. A model of preventive maintenance for Buhehr nuclear power plant which is due to be completed by 2001 is developed. The prescribed model is based on past experiences of VVER nuclear power plants around the world. The utilized data is provided by International Atomic Energy Agency (IAEA) in Vienna, Austria. The data and past experiences reveal such important information as availability, energy loss, types of failures, duration of failure, etc. A strategy for designing a database is established. These data are then analyzed by statistical methods such as Pareto analysis, t-test, K-S test, analysis of variance, etc. The results of our analysis reveal important information in regard to establishment of a well-defined preventive maintenance programme in Buhshehr nuclear power plant. The results show that certain equipment such turbo-generator and control-rods play an important role in the maintenance of a VVER nuclear power plant. Other findings are discussed in great detail

Regional siting survey for thermal power plants in the state of Ohio

International Nuclear Information System (INIS)

Elkins, M.L.; DiNunno, J.J.

1975-01-01

The selection and evaluation of sites for power plants have become increasingly difficult in recent years as pressures from various societal segments have resulted in government restraints on selection and burning of fossil fuels, on methods of heat dissipation, on acquisition of transmission line rights-of-way, and on environmental impact in general. The key elements in successful application of power plant siting technology are the development of the proper balance among the basic siting considerations and the understanding that level of detail in a study varies in an inverse relationship with the siting area under examination. As the first step in the process of selection and eventual licensing of new thermal power plant sites for a utility in the State of Ohio, the entire state was screened to determine promising candidate regions large enough to offer several possible candidate sites for thermal power plants. Because of the size of the area under consideration and the advantages of developing sites with an ultimate capacity for more than one power plant, sites with an installed capacity of 1100 to 4400 MW(e) were considered for this study. As a result of the preliminary screening conducted in four distinct steps, three candidate regions showed the best overall promise for either nuclear or fossil-fueled power plant development. Tentative identification was made of candidate sites within these candidate regions, and follow-on studies conducted in an increasing level of detail are presently in progress to determine the candidate site(s) most promising for power plant siting. (U.S.)

Maximum power point tracker for photovoltaic power plants

Science.gov (United States)

Arcidiacono, V.; Corsi, S.; Lambri, L.

The paper describes two different closed-loop control criteria for the maximum power point tracking of the voltage-current characteristic of a photovoltaic generator. The two criteria are discussed and compared, inter alia, with regard to the setting-up problems that they pose. Although a detailed analysis is not embarked upon, the paper also provides some quantitative information on the energy advantages obtained by using electronic maximum power point tracking systems, as compared with the situation in which the point of operation of the photovoltaic generator is not controlled at all. Lastly, the paper presents two high-efficiency MPPT converters for experimental photovoltaic plants of the stand-alone and the grid-interconnected type.

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

International Nuclear Information System (INIS)

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

Safety-related incidents at the Finnish nuclear power plants

International Nuclear Information System (INIS)

Lehtinen, P.

1986-03-01

This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Reports, Operation of Finnish Nuclear Power Plants, which are supplemented by this report intended for experts. (author)

Safety-related incidents at the Finnish nuclear power plants

International Nuclear Information System (INIS)

Lehtinen, P.

1985-01-01

This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Reports, Operation of Finnish Nuclear Power Plants, which are supplemented by this report intended for experts. (author)

Port Menier thermal power plant: Pre-project report

International Nuclear Information System (INIS)

1992-02-01

Port Menier, the town on Anticosti Island in the St Lawrence River estuary, is supplied with electricity from a diesel power plant having a firm capacity of 1,080 kW. Since 1987, power demand has increased at an average annual rate of 5.7%, raising the winter peak demand from 670 kW to 987 kW. The power plant is located in the center of town and is obsolete, presenting a number of architectural, environmental, and operational deficiencies. It is proposed to construct a new power plant having an initial firm capacity of 1,490 kW and storage capacity for 75,000 liters of fuel. The plant site will have an area of ca 6,265 m 2 to allow for an eventual expansion to over 3,000 kW capacity, sufficient for satisfying forecast demand over the next 20 years. Estimated cost of the new plant is ca $9.5 million. The old plant will be decommissioned and the new plant will be built at a site outside of town. The natural and human environments characteristic of the Port Menier area are detailed and the two selected sites for the new plant are described and compared. A site in the industrial zone of Port-Menier is favored. The environmental impacts of the new plant are analyzed and mitigation measures during the preconstruction, construction, and operational phases are proposed. Local economic impacts are estimated at around $990,000. 20 refs., 12 figs., 12 tabs

Collection and evaluation of complete and partial losses of off-site power at nuclear power plants

International Nuclear Information System (INIS)

Battle, R.E.

1985-02-01

Events involving loss of off-site power that have occurred at nuclear power plants through 1983 are described and categorized as complete or partial losses. The events were identified as plant-centered or grid-related failures. In addition, the causes of the failures were classified as weather, human error, design error, or hardware failure. The plant-centered failures were usually of shorter duration than the weather-related grid failures. For this reason, the weather-related events were reviewed in detail. Design features that may be important factors affecting off-site power system reliability were tabulated for most of the operating nuclear power plants. The tabulated information was provided to NRC for a statistical analysis to determine the importance of these design features for losses of off-site power. The frequency of losses of off-site power versus duration was estimated for three time periods. The frequency of loss of off-site power was estimated to be 0.09/reactor-year based on industry-wide data for the years 1959 through 1983

State regulation and power plant productivity: background and recommendations

International Nuclear Information System (INIS)

1980-09-01

This report was prepared by representatives of several state regulatory agencies. It is a guide to some of the activities currently under way in state agencies to promote increased availability of electrical generating power plants. Standard measures of plant performance are defined and the nature of data bases that report such measures is discussed. It includes reviews of current state, federal, and industry programs to enhance power plant productivity and provides detailed outlines of programs in effect in California, Illinois, Michigan, New York, North Carolina, Ohio, and Texas. A number of actions are presented that could be adopted by state regulatory agencies, depending on local conditions. They include: develop a commission position or policy statement to encourage productivity improvements by utilities; coordinate state efforts with ongoing industry and government programs to improve the acquisition of power plant performance data and the maintenance of quality information systems; acquire the capability to perform independent analyses of power plant productivity; direct the establishment of productivity improvement programs, including explicit performance objectives for both existing and planned power plants, and a performance program; establish a program of incentives to motivate productivity improvement activities; and participate in ongoing efforts at all levels and initiate new actions to promote productivity improvements

Safety-related occurrences at the Finnish nuclear power plants

International Nuclear Information System (INIS)

Reponen, H.; Viitasaari, O.

1985-04-01

This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Report for this period, Operation of Finnish Nuclear Power Plants (STUK-B-YTO 7), which is supplemented by this report intended for experts. (author)

Seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Senne Junior, M.

1983-01-01

A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those Plants, against the action of earthquakes is described. The instrumentation described is based on the nuclear standards in force. The minimum amount of sensors and other components used, as well as their general localization, is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The various devices used are not covered in detail, except for the accelerometer, which is the seismic instrumentation basic component. (Author) [pt

Independent verification in operations at nuclear power plants: Summaries of site visits

International Nuclear Information System (INIS)

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

1995-09-01

A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries was conducted and are detailed in volume 1. This paper is a compilation of the visits to nuclear power plant sites to study independent verification in operations at sites in Canada, USA, Japan, United Kingdom, France and Germany. 3 tabs., 22 figs

Safety principles and design management of Chashma Nuclear Power Plant

International Nuclear Information System (INIS)

Geng Qirui; Cheng Pingdong

1997-01-01

The basic safety consideration and detailed design principles in the design of Chashma Nuclear Power Plant is elaborated. The management within the frame setting up by 'safety culture' and 'quality culture'

Optimization of operation for combined heat and power plants - CHP plants - with heat accumulators using a MILP formulation

Energy Technology Data Exchange (ETDEWEB)

Grue, Jeppe; Bach, Inger [Aalborg Univ. (Denmark). Inst. of Energy Technology]. E-mails: jeg@iet.auc.dk; ib@iet.auc.dk

2000-07-01

The power generation system in Denmark is extensively based on small combined heat and power plants (CHP plants), producing both electricity and district heating. This project deals with smaller plants spread throughout the country. Often a heat accumulator is used to enable electricity production, even when the heat demand is low. This system forms a very complex problem, both for sizing, designing and operation of CHP plants. The objective of the work is the development of a tool for optimisation of the operation of CHP plants, and to even considering the design of the plant. The problem is formulated as a MILP-problem. An actual case is being tested, involving CHP producing units to cover the demand. The results from this project show that it is of major importance to consider the operation of the plant in detail already in the design phase. It is of major importance to consider the optimisation of the plant operation, even at the design stage, as it may cause the contribution margin to rise significantly, if the plant is designed on the basis of a de-tailed knowledge of the expected operation. (author)

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Energy reserves and power plants in the USSR

Energy Technology Data Exchange (ETDEWEB)

Madaus, C

1971-12-01

Solid fuels are still of primary importance in the USSR. Coal reserves and production rates are outlined. Natural gas reserves are estimated to be about 70 x 10/sup 18/m/sup 3/, with operational fields having a capacity of about 12.1 x 10/sup 18/m/sup 3/. Detailed data concerning gas and hydrodynamic reserves, energy production statistics, and high-capacity condensation-turbines are tabulated. Extensive technical data is also provided concerning installed nuclear, thermal, and hydroelectric power plants. Solar energy remains in very early stages of development. In some areas, particularly the foothills of the Caucasus, Kirim, and Kamchatka, conditions are highly favorable for the development of geothermal power plants. A geothermal installation is planned for Kamchatka. It will have a capacity of 700-850 MW, and will be driven by thermal waters arising from the Awatschinskaja Sopka volcano. Four tidal power-plants were planned for construction by 1976. The first was completed in 1968, at the Barent Sea. One of these plants will have a capacity of 30-35 TWh/annum.

Less power plants

International Nuclear Information System (INIS)

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

Ground assessment methods for nuclear power plant

International Nuclear Information System (INIS)

1985-01-01

It is needless to say that nuclear power plant must be constructed on the most stable and safe ground. Reliable assessment method is required for the purpose. The Ground Integrity Sub-committee of the Committee of Civil Engineering of Nuclear Power Plant started five working groups, the purpose of which is to systematize the assessment procedures including geological survey, ground examination and construction design. The works of working groups are to establishing assessment method of activities of faults, standardizing the rock classification method, standardizing assessment and indication method of ground properties, standardizing test methods and establishing the application standard for design and construction. Flow diagrams for the procedures of geological survey, for the investigation on fault activities and ground properties of area where nuclear reactor and important outdoor equipments are scheduled to construct, were established. And further, flow diagrams for applying investigated results to design and construction of plant, and for determining procedure of liquidification nature of ground etc. were also established. These systematized and standardized methods of investigation are expected to yield reliable data for assessment of construction site of nuclear power plant and lead to the safety of construction and operation in the future. In addition, the execution of these systematized and detailed preliminary investigation for determining the construction site of nuclear power plant will make much contribution for obtaining nation-wide understanding and faith for the project. (Ishimitsu, A.)

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

1992-01-01

The Code on Design (Safety Series 50-C-D (Rev. 1)) within the NUSS (Nuclear Safety Standards) programme of the IAEA points out the necessity of measures for protecting plant items which are important to safety against fires of internal and external origin. Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice. Figs, 1 tab

Financial and ratepayer impacts of nuclear power plant regulatory reform

International Nuclear Information System (INIS)

Turpin, A.G.

1985-01-01

Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports

Thermoeconomic studies applied to maintenance of power plants

International Nuclear Information System (INIS)

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

Demographic comparison of the Barsebaeck nuclear power plant with plants situated near large cities and national borders

International Nuclear Information System (INIS)

Walmod-Larsen, O.; Starcke, K.

1984-06-01

The Swedish-Danish Barsebaeck committee suggested in June 1983 that a demographic comparison of the Barsebaeck nuclear power plant be made with plants situated near other large cities and national borders. Sixteen other nuclear power plants: 13 in Western Europe, 2 in USA and 1 in Canada were chosen for the comparison. For five discrete distances out to 50 km, the population distributions have been found and compared. In addition the positions, related to the plants, of institutions, administrative centres, communication centres and other plants of public importance within the country or in neughbouring countries are described. Finally, the details of special agreements are given together with negotiations between neighbouring countries or internationally about nuclear power related matters. These include alarm and emergency procedures and agreements about liability in case of an accident in a neighbouring country. (author)

Nuclear power plant design characteristics. Structure of nuclear power plant design characteristics in the IAEA Power Reactor Information System (PRIS)

International Nuclear Information System (INIS)

2007-03-01

One of the IAEA's priorities has been to maintain the Power Reactor Information System (PRIS) database as a viable and useful source of information on nuclear reactors worldwide. To satisfy the needs of PRIS users as much as possible, the PRIS database has included also a set of nuclear power plant (NPP) design characteristics. Accordingly, the PRIS Technical Meeting, organized in Vienna 4-7 October 2004, initiated a thorough revision of the design data area of the PRIS database to establish the actual status of the data and make improvements. The revision first concentrated on a detailed review of the design data completion and the composition of the design characteristics. Based on the results of the review, a modified set and structure of the unit design characteristics for the PRIS database has been developed. The main objective of the development has been to cover all significant plant systems adequately and provide an even more comprehensive overview of NPP unit designs stored in the PRIS database

Nuclear power plants

International Nuclear Information System (INIS)

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

Safety-related occurrences at the Finnish nuclear power plants

International Nuclear Information System (INIS)

Viitasaari, O.; Rantavaara, A.

1984-03-01

This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Report for this period, Operation of Finnish Nuclear Power Plants (STL-B-RTO-83/7), which is supplemented by this report intended principally for experts. (author)

Seismic design of equipment and piping systems for nuclear power plants in Japan

International Nuclear Information System (INIS)

Minematsu, Akiyoshi

1997-01-01

The philosophy of seismic design for nuclear power plant facilities in Japan is based on 'Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981' (referred to as 'Examination Guide' hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in 'Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association'. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

Seismic design of equipment and piping systems for nuclear power plants in Japan

Energy Technology Data Exchange (ETDEWEB)

Minematsu, Akiyoshi [Tokyo Electric Power Co., Inc. (Japan)

1997-03-01

The philosophy of seismic design for nuclear power plant facilities in Japan is based on `Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981` (referred to as `Examination Guide` hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in `Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association`. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

Accident prevention in power plants

International Nuclear Information System (INIS)

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

Geodesy problems in nuclear power plant construction

International Nuclear Information System (INIS)

Eory, K.

1981-01-01

The special geodetic problems encountered during the construction of the Paks nuclear power plants are treated. The main building with its hermetically connected components including the reactor, the steam generators, the circulation pumps etc. impose special requirements on the control net of datum points. The geodesy tasks solved during the construction of the main building are presented in details. (R.P.)

Structural health monitoring of power plant components based on a local temperature measurement concept

International Nuclear Information System (INIS)

Rudolph, Juergen; Bergholz, S.; Hilpert, R.; Jouan, B.; Goetz, A.

2012-01-01

The fatigue assessment of power plant components based on fatigue monitoring approaches is an essential part of the integrity concept and modern lifetime management. It is comparable to structural health monitoring approaches in other engineering fields. The methods of fatigue evaluation of nuclear power plant components based on realistic thermal load data measured on the plant are addressed. In this context the Fast Fatigue Evaluation (FFE) and Detailed Fatigue Calculation (DFC) of nuclear power plant components are parts of the three staged approach to lifetime assessment and lifetime management of the AREVA Fatigue Concept (AFC). The three stages Simplified Fatigue Estimation (SFE), Fast Fatigue Evaluation (FFE) and Detailed Fatigue Calculation (DFC) are characterized by increasing calculation effort and decreasing degree of conservatism. Their application is case dependent. The quality of the fatigue lifetime assessment essentially depends on one hand on the fatigue model assumptions and on the other hand on the load data as the basic input. In the case of nuclear power plant components thermal transient loading is most fatigue relevant. Usual global fatigue monitoring approaches rely on measured data from plant instrumentation. As an extension, the application of a local fatigue monitoring strategy (to be described in detail within the scope of this paper) paves the way of delivering continuously (nowadays at a frequency of 1 Hz) realistic load data at the fatigue relevant locations. Methods of qualified processing of these data are discussed in detail. Particularly, the processing of arbitrary operational load sequences and the derivation of representative model transients is discussed. This approach related to realistic load-time histories is principally applicable for all fatigue relevant components and ensures a realistic fatigue evaluation. (orig.)

Direct FuelCell/Turbine Power Plant

Energy Technology Data Exchange (ETDEWEB)

Hossein Ghezel-Ayagh

2008-09-30

to the system, was demonstrated. System analyses of 40 MW DFC/T hybrid systems, approaching 75% efficiency on natural gas, were carried out using CHEMCAD simulation software. The analyses included systems for near-term and long-term deployment. A new concept was developed that was based on clusters of one-MW fuel cell modules as the building blocks. The preliminary design of a 40 MW power plant, including the key equipment layout and the site plan, was completed. The process information and operational data from the proof-of-concept tests were used in the design of 40 MW high efficiency DFC/T power plants. A preliminary cost estimate for the 40 MW DFC/T plant was also prepared. Pilot-scale tests of the cascaded fuel cell concept for achieving high fuel utilizations were conducted. The tests demonstrated that the concept has the potential to offer higher power plant efficiency. Alternate stack flow geometries for increased power output and fuel utilization capabilities were also evaluated. Detailed design of the packaged sub-MW DFC/T Alpha Unit was completed, including equipment and piping layouts, instrumentation, electrical, and structural drawings. The lessons learned from the proof-of-concept tests were incorporated in the design of the Alpha Unit. The sub-MW packaged unit was fabricated, including integration of the Direct FuelCell{reg_sign} (DFC{reg_sign}) stack module with the mechanical balance-of-plant and electrical balance-of-plant. Factory acceptance tests of the Alpha DFC/T power plant were conducted at Danbury, CT. The Alpha Unit achieved an unsurpassed electrical efficiency of 58% (LHV natural gas) during the factory tests. The resulting high efficiency in conversion of chemical energy to electricity far exceeded any sub-MW class power generation equipment presently in the market. After successful completion of the factory tests, the unit was shipped to the Billings Clinic in Billings, MT, for field demonstration tests. The DFC/T unit accomplished a

Safety evaluation of nuclear power plant against the virtual tsunami

International Nuclear Information System (INIS)

Chin, S. B.; Imamura, Fumihiko

2004-01-01

The main scope of this study is the numerical analysis of virtual tsunami event near the Ulchin Nuclear Power Plants. In the numerical analysis, the maximum run-up height and draw-down are estimated at the Ulchin Nuclear Power Plants. The computer program developed in this study describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. It can be used to check the safety of a nuclear power plant against tsunami attacks. The program can also be used to calculate run-up height of wave and provide proper design criteria for coastal facilities and structures. A maximum inundation zone along the coastline can be developed by using the moving boundary condition. As a result, it is predicted that the Ulchin Nuclear Power Plants might be safe against the virtual tsunami event. Although the Ulchin Nuclear Power Plants are safe against the virtual tsunami event, the occurrence of a huge tsunami in the seismic gap should be investigated in detail. Furthermore, the possibility of nearshore tsunamis around the Korean Peninsula should also be studied and monitored continuously

Demands on thermal power plants in the liberalised energy market

International Nuclear Information System (INIS)

Hein, D.; Kwanka, K.; Fischer, T.

2005-01-01

In the liberalised energy market, a diversified set (''mix'') of power plants will be needed. By investigating present and anticipated future criteria in detail, available technologies and outlines of further development are identified and discussed. Among them, concepts for efficiency-optimised base load plants as well as units with an improved cycling operation capability are both attributed to a specific valued benefit. Following the demand for a significant reduction of the overall greenhouse gas emissions, centralised power plants fed by fossil fuels and modified for retention of CO 2 are needed to guarantee a supply of energy at moderate costs in the 21st century. (author)

Assessment of the overall fire safety arrangements at nuclear power plants

International Nuclear Information System (INIS)

1996-01-01

The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire safety of nuclear power plants. The publication comprises a detailed checklist of the specific elements to be addressed when assessing the adequacy and effectiveness of the overall fire safety arrangements of operating nuclear power plants. The publication will be useful not only to regulators and safety assessors but also to operators and designers. The book addresses a specialized topic outlined in Safety Guide No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, and it is recommended that it be used in conjunction with this Safety Series publication

The program of reactors and nuclear power plants

International Nuclear Information System (INIS)

Calabrese, Carlos R.

2001-01-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

Exergy evaluation of a typical 330 MW solar-hybrid coal-fired power plant in China

International Nuclear Information System (INIS)

Peng, Shuo; Wang, Zhaoguo; Hong, Hui; Xu, Da; Jin, Hongguang

2014-01-01

Highlights: • Exergy analysis of solar-hybrid coal-fired power plant has been processed. • EUD method is utilized to obtain detailed information on the exergy destruction in each process. • Off-design thermodynamic performances are discussed to identify the advantages. • Exergy destruction of several parts under varying solar radiation is examined. - Abstract: This study discusses the thermodynamic performance of a solar-hybrid coal-fired power plant that uses solar heat with temperature lower than 300 °C to replace the extracted steam from a steam turbine to heat the feed water. Through this process, the steam that was to be extracted can efficiently expand in the steam turbine to generate electricity. The flow rate of steam returning to the turbine retains only a small part of the main stream, allowing the steam turbine to run close to design conditions for all DNI. A solar-only thermal power plant without storage is also discussed to illustrate the advantages of a solar-hybrid coal-fired power plant. The off-design performances of both plants are compared based on the energy-utilization diagram method. The exergy destruction of the solar-hybrid coal-fired power plant is found to be lower than that of the solar-only thermal power plant. The comparison of two plants, which may provide detailed information on internal phenomena, highlights several advantages of the solar-hybrid coal-fired power plant in terms of off-design operation: lower exergy destruction in the solar feed water heater and steam turbine and higher exergy and solar-to-electricity efficiency. Preliminary technological economic performances of both plants are compared. The results obtained in this study indicate that a solar-hybrid coal-fired power plant could achieve better off-design performance and economic performance than a solar-only thermal power plant

The long term plan for the integration of nuclear power plants into the Turkish Electrical Power System

International Nuclear Information System (INIS)

Kutukcuoglu, A.

1974-03-01

The report covers in detail the study of the expansion of the Turkish Electric Power System for the period 1980-1987. Load forecast is done by sectors and regions and inter-regions power balances gave the basis for the high voltage network configurations. Expansion alternatives are defined giving priority to hydroelectric projects, to local resources and nuclear power plants concurrently with conventional plants (lignite and oil). Several reactor strategies are analysed with LWR, HWR, FBR and HTGR power plants. Present worth value method is used for comparison of alternatives and sensitivity analysis is done for those ranked in the first places. Load flow, transient stability and frequency deviation studies of the power system are studied carefully by means of A.C. calculator and digital computer codes in order to see the influence of the introduction of large-sized power plants (600-750MW(e)) and their location in the power system. A 600MW(e) nuclear plant in 1983 and a second one of 750MW(e) in 1987 should, it is found, be commissioned into the system. The economic optimization was done with two computer programmes developed by KFA (Juelich): IACO for fuelling nuclear plant and RESTRAPO for power system with high hydroelectric component. The report is bound in three volumes: Volume I: Summary and Conclusions; Volume II: System Planning; Volume III: Electrical Survey

The performance of the Armenia Nuclear Power Plant and power facilities in the 1988 Armenia earthquake

International Nuclear Information System (INIS)

Yanev, P.I.

1989-01-01

The speaker presents the geology, seismology, and effects of the Armenian earthquake which occured on December 7,1988. This is a highly industrialized area with numerous power plants, including one nuclear power plant in addition to several conventional plants. The response of the nuclear plant to the earthquake is described in detail, and the speaker concludes with an outline of suggestions which could help with earthquake preparedness in the United States, particularly in Puget Sound, Washington; along the New Madrid in Missouri and Tennessee;in the Charleston ,South Carolina area; and in the Salt Lake City region of Utah. All of these areas have similar earthquake potential, building types, absence of earthquake preparedness programs, the possibility of an earthquake of comparable proportions as Armenia

Reactor instrumentation and control in nuclear power plants in Germany

International Nuclear Information System (INIS)

Aleite, W.

1993-01-01

The pertinent legislation, guidelines and standards of importance for nuclear power plant construction as well as the relevant committees in Germany are covered. The impact of international developments on the German regulatory scene is mentioned. A series of 15 data sheets on reactor control, followed by 5 data sheets on instrumentation and control in nuclear power plants, which were drawn up for German plants, are compared and commented in some detail. Digitalization of instrumentation and control systems continues apace. To illustrate the results that can be achieved with a digitalized information system, a picture series that documents a plant test of behavior on simulated steam generator tube rupture is elaborately commented. An outlook on backfitting and upgrading applications concludes this paper. (orig.) [de

Turbines for nuclear power plants. 2.ed.

International Nuclear Information System (INIS)

Troyanovskij, B.M.

1978-01-01

In the second edition of the book considered are practically all the main problems of calculation and operation of turbines and turbine installations of nuclear power plants. As compared to the first edition, essentially addes is the reproduction of the problem on combined generation of heat and electric energy. Also represented is detailed material on methods of preliminary evaluation of turbine effectiveness. Considered are peculiarities of turbine operation on wet steam and the basis of their thermal calculation. Much attention is payed to the problem of wet stream current in the turbine elements and wetness effect on their characteristics. Problems of wetness separation and moving blade erosion as well as other turbine elements are extracted in a special section. Given are structural schemes of different methods of innerchannel and periphery wet removal as well as experimental materials on their effectiveness. Given are descriptions and critical analysis of a great number of typical constructions of nuclear power plant steam turbines, produced by native plants as well as by the main foreign firms. Considered also are constructions of outside separators and steam superheaters. Separately given is the problem of rotation frequency choise of nuclear power plant wet steam turbines. Represented are materials on turbine installation tests, considered are the problems of turbine starting and manoeuvrability, analyzed are their typical jailures and damages. One of the sections of the book is devoted to gas turbine installations of nuclear power plants. Different material on this theme scattered before in various sources is summarized in the book

Distributed control and data processing system with a centralized database for a BWR power plant

International Nuclear Information System (INIS)

Fujii, K.; Neda, T.; Kawamura, A.; Monta, K.; Satoh, K.

1980-01-01

Recent digital techniques based on changes in electronics and computer technologies have realized a very wide scale of computer application to BWR Power Plant control and instrumentation. Multifarious computers, from micro to mega, are introduced separately. And to get better control and instrumentation system performance, hierarchical computer complex system architecture has been developed. This paper addresses the hierarchical computer complex system architecture which enables more efficient introduction of computer systems to a Nuclear Power Plant. Distributed control and processing systems, which are the components of the hierarchical computer complex, are described in some detail, and the database for the hierarchical computer complex is also discussed. The hierarchical computer complex system has been developed and is now in the detailed design stage for actual power plant application. (auth)

Off-shore nuclear power plant

International Nuclear Information System (INIS)

Nakanishi, T.

1980-01-01

In order to avoid losses of energy and seawater pollution an off-shore nuclear power plant is coupled with a power plant which utilizes the temperature difference between seawater and hot reactor cooling water. According to the invention the power plant has a working media loop which is separated from the nuclear power plant. The apparative equipment and the operational characteristics of the power plant are the subject of the patent. (UWI) [de

Solar thermal power plants

International Nuclear Information System (INIS)

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)

The working lifetime of nuclear power plants and new types of power reactors

International Nuclear Information System (INIS)

Bataille, Ch.; Birraux, C.

2003-01-01

The report on the working lifetime of nuclear power plants and new reactor types, by Mr Christian Bataille, deputy for the Nord, and Mr Claude Birraux, deputy for Haute-Savoie as well as President of the Office, supplements the studies carried out by the Parliamentary Office on the Safety of Nuclear Installations and Radioactive Wastes: it examines the remaining working life of the EDF nuclear power plants and the current status of projects that might, if circumstances were right, replace the reactors at present in service. The report investigates the different physical and other factors that influence the ageing of nuclear power plants and tackles the question of whether the design life of 40 years could be exceeded in practice. The whole issue of French nuclear power plant is put in perspective and compared with the situation of nuclear plants in Finland, Sweden, Germany and the United States, from the technical and regulatory standpoints. Believing that any attempt to optimise the working lifetime of the power plants currently in service must be accompanied by simultaneous moves aimed at their replacement, Messrs. Christian Bataille and Claude Birraux go on to review in detail the various light water reactor projects being proposed around the world for completion by 2015, as developments of existing models, in particular the EPR reactor of Framatome ANP, characterised by its competitiveness. They suggest that a first such reactor should be built as quickly as possible. Describing the other nuclear systems being investigated by research organisations not only in France but also in the United States and Sweden, Mrs. Christian Bataille and Claude Birraux review the objectives of these and the circumstances in which they might be developed, which would be unlikely to be before 2035 in view of the technological problems to be overcome and the industrial demonstration plants that would be needed

Power plant cycle chemistry - a currently neglected power plant chemistry discipline

International Nuclear Information System (INIS)

Bursik, A.

2005-01-01

Power plant cycle chemistry seems to be a stepchild at both utilities and universities and research organizations. It is felt that other power plant chemistry disciplines are more important. The last International Power Cycle Chemistry Conference in Prague may be cited as an example. A critical review of the papers presented at this conference seems to confirm the above-mentioned statements. This situation is very unsatisfactory and has led to an increasing number of component failures and instances of damage to major cycle components. Optimization of cycle chemistry in fossil power plants undoubtedly results in clear benefits and savings with respect to operating costs. It should be kept in mind that many seemingly important chemistry-related issues lose their importance during forced outages of units practicing faulty plant cycle chemistry. (orig.)

Modern handling and monitoring concepts for nuclear power plants

International Nuclear Information System (INIS)

Hofmann, H.; Lochner, K.H.

1989-01-01

Advanced microprocessor technology offers new means and methods also to power plant operation to improve the man-machine interface by using VDU's for process control, thus enhancing plant safety and reliability. A future control-room concept involving operation and monitoring to be effected by means of VDU's exclusively, calls for a detailed knowledge of the requirements which are made by the process and the operator on the system, and for the application of a very powerful microprocessor technology. Visualization of operating and monitoring processes matched to the needs of operators should be possible at high functionality and display quality without substantial restrictions caused by the device technology used. (orig.) [de

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

DEFF Research Database (Denmark)

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...

System analysis and mass balance of a caloric power plant

International Nuclear Information System (INIS)

Schachermayer, E.; Rechberger, H.; Brunner, P.H.; Maderner, W.

1995-05-01

The present feasibility study analyses the possibilities of examining and presenting material and energy aspects of the interaction between the power plant and the region. A method has been worked out to establish an overall system called power plant and its periphery which combines the thermal power plant Voitsberg 3, the supplying coal mine Oberdorf, and the ash dumping site Karlschacht 2. One goal of this study was therefore, to find a way of combining the different steps 'mining' , 'power plant' , and 'ash dumping' to an overall system considering both qualitative and quantitative aspects. Another goal of the present feasibility study was to develop methods to consider the impacts of the power plant and its periphery to the environment and the use of resources. For this purpose the region is analysed from two different points of view: - the region defined by the 'product'; its size is defined by the number of inhabitants the power plant supplies with the product 'electricity'. The region defined by the area, in which the specific impacts of the power plant on air, water, soil etc. have to be examined; its size will therefore vary considerably according to the subject of investigation. Based on data provided by the power plant operators a rough estimate could be made to what extent the power plant is responsible for the air pollutant emissions in the region defined by the 'product'. According to these data the part of pollution caused by the power plant amounts to 10% for NOx and particulate matter, to 40% for SO 2 , and to 70% for CO 2 . Furthermore, it can be seen, that the material fluxes of selenium and mercury have to be surveyed in more detail. The ashes dumped in Karlschacht 2 contain a large amount of heavy metals, mainly arsenic, selenium, and mercury. These elements occur in a much higher concentration than in the earth crust. (author)

Alternative off-site power supply improves nuclear power plant safety

International Nuclear Information System (INIS)

Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

2014-01-01

Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

Safety-specific benefit of the probabilistic evaluation of older nuclear power plants

International Nuclear Information System (INIS)

Hoertner, H.; Koeberlein, K.

1991-01-01

The report summarizes the experience of the GRS obtained within the framework of a probabilistic evaluation of older nuclear power plants and the German risk study. The applied methodology and the problems involved are explained first. After a brief summary of probabilistic analyses carried out for German nuclear power plants, reliability analyses for older systems are discussed in detail. The findings from the probabilistic safety analyses and the conclusions drawn are presented. (orig.) [de

CONCEPT-5 user's manual. [Power plant costs

Energy Technology Data Exchange (ETDEWEB)

Hudson, C.R. II

1979-01-01

The CONCEPT computer code package was developed to provide conceptual capital cost estimates for nuclear-fueled and fossil-fired power plants. Cost estimates can be made as a function of plant type, size, location, and date of initial operation. The output includes a detailed breakdown of the estimate into direct and indirect costs similar to the accounting system described in document NUS--531. Cost models are currently provided in CONCEPT 5 for single- and multiunit pressurized-water reactors, boiling-water reactors, and cost-fired plants with and without flue gas desulfurization equipment.

Diagnostic knowledge generation of nuclear power plants using knowledge compilers

International Nuclear Information System (INIS)

Yoshikawa, Shinji; Endou, Akira; Ikeda, Mitsuru; Mizoguchi, Riichiro

1994-01-01

This paper discusses a method to generate diagnostic knowledge of nuclear power plants, from commonly accepted physical knowledge and design information about plant configuration. This method is based on qualitative reasoning, which is advantageous to numerical information processing in the sense that system can explain why and how directly applicable knowledge is correctly generated, and that knowledge base is highly reusable and expandable because it is independent on detailed numerical design specifications. However, reasoning ambiguity has been found as the largest problem in applying the technique to nuclear power plants. The proposed approach mainly consists of a knowledge representation scheme, reasoning algorithm, and qualitative model construction method. (author). 4 refs, 8 figs, 1 tab

Preoperational ALARA walk-down at the Shearon Harris Nuclear Power Plant

International Nuclear Information System (INIS)

Greene, D.W.

1987-01-01

Carolina Power and Light Company's Shearon Harris Nuclear Power Plant will enter commercial operation in 19987. During its design and construction a number of reviews were performed to ensure that personnel exposures in the completed plant would be ALARA. The final review in this process consisted of a comprehensive walk-down of plant radiation controlled areas by health physics, operations, maintenance, and engineering personnel. The walk-down project was conducted over a 12-month period using detailed criteria and checklists. This article describes the project, presents examples of the criteria that were used, and list the problems that were identified for resolution as well as the good ALARA design features that were incorporated into the plant

Investigation of occurrences of loss of external power supply in Spanish nuclear power plants

International Nuclear Information System (INIS)

Conde, J.M.; Reig, J.

1989-01-01

The paper reports on an investigation undertaken by the Nuclear Safety Council into occurrences of loss of external power supply in Spanish light water plants between 1981 and 1987. During this period all of the plants investigated (nine), with the exception of one, experienced an event of this type. The causes, effects and duration of each are studied in detail and the conclusion is drawn that the main cause of this type of occurrence is the intrinsic instability of the Spanish national grid. The response of plants to these various failures in external power supply was studied, special attention being paid to the correct operation of safety systems. In addition, the behaviour of other systems not related to safety is discussed, as are modifications and actions taken as a result of accumulated experience with a view to improving the plant response in the event of the failure of the external power supply, and reducing the frequency of such occurrences and their effective duration. The data obtained from this analysis were compared with those obtained in studies performed in other countries and the conclusion was drawn that failures in the external power supply occur slightly more frequently in Spain than in other countries. Similarly, a comparison was drawn between plant response during an actual failure and the response obtained during loss of external power nuclear tests which are carried out in all Spanish plants during the startup (commissioning) programme, in order to ascertain whether the test itself is adequate. (author). 1 fig., 3 tabs

Thermoeconomic analysis of a power/water cogeneration plant

International Nuclear Information System (INIS)

Hamed, Osman A.; Al-Washmi, Hamed A.; Al-Otaibi, Holayil A.

2006-01-01

Cogeneration plants for simultaneous production of water and electricity are widely used in the Arabian Gulf region. They have proven to be more thermodynamically efficient and economically feasible than single purpose power generation and water production plants. Yet, there is no standard or universally applied methodology for determining unit cost of electric power generation and desalinated water production by dual purpose plants. A comprehensive literature survey to critically assess and evaluate different methods for cost application in power/water cogeneration plants is reported in this paper. Based on this analysis, an in-depth thermoeconomic study is carried out on a selected power/water cogeneration plant that employs a regenerative Rankine cycle. The system incorporates a boiler, back pressure turbine (supplying steam to two MSF distillers), a deaerator and two feed water heaters. The turbine generation is rated at 118 MW, while MSF distiller is rated at 7.7 MIGD at a top brine temperature of 105 deg. C. An appropriate costing procedure based on the available energy accounting method which divides benefits of the cogeneration configuration equitably between electricity generation and water production is used to determine the unit costs of electricity and water. Capital charges of common equipment such as the boiler, deaerator and feed water heaters as well as boiler fuel costs are distributed between power generated and desalinated water according to available energy consumption of the major subsystems. A detailed sensitivity analysis was performed to examine the impact of the variation of fuel cost, load and availability factors in addition to capital recovery factor on electricity and water production costs

Control of power plants and power systems. Proceedings

International Nuclear Information System (INIS)

Canales-Ruiz, R.

1996-01-01

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

Modularization Technology in Power Plant Construction

International Nuclear Information System (INIS)

Kenji Akagi; Kouichi Murayama; Miki Yoshida; Junichi Kawahata

2002-01-01

Since the early 1980's, Hitachi has been developing and applying modularization technology to domestic nuclear power plant construction, and has achieved great rationalization. Modularization is one of the plant construction techniques which enables us to reduce site labor by pre-assembling components like equipment, pipes, valves and platforms in congested areas and installing them using large capacity cranes for cost reduction, better quality, safety improvement and shortening of construction time. In this paper, Hitachi's modularization technologies are described especially from with respect to their sophisticated design capabilities. The application of 3D-CAD at the detailed layout design stage, concurrent design environment achieved by the computer network, module design quantity control and the management system are described. (authors)

Dynamic Models for Wind Turbines and Wind Power Plants

Energy Technology Data Exchange (ETDEWEB)

Singh, M.; Santoso, S.

2011-10-01

The primary objective of this report was to develop universal manufacturer-independent wind turbine and wind power plant models that can be shared, used, and improved without any restrictions by project developers, manufacturers, and engineers. Manufacturer-specific models of wind turbines are favored for use in wind power interconnection studies. While they are detailed and accurate, their usages are limited to the terms of the non-disclosure agreement, thus stifling model sharing. The primary objective of the work proposed is to develop universal manufacturer-independent wind power plant models that can be shared, used, and improved without any restrictions by project developers, manufacturers, and engineers. Each of these models includes representations of general turbine aerodynamics, the mechanical drive-train, and the electrical characteristics of the generator and converter, as well as the control systems typically used. To determine how realistic model performance is, the performance of one of the models (doubly-fed induction generator model) has been validated using real-world wind power plant data. This work also documents selected applications of these models.

Modeling and simulation of pressurized water reactor power plant

International Nuclear Information System (INIS)

Wang, S.J.

1983-01-01

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

Structural experiences at the Kewaunee Nuclear Power Plant

International Nuclear Information System (INIS)

Setlur, A.V.

1983-01-01

This paper discusses the original structural and geotechnical design and subsequent structural experience at the Kewaunee Nuclear Power Plant. The original design of the 535 MWe Westinghouse two loop PWR nuclear plant operated by Wisconsin Public Service Corporation, was started in 1967 and was completed in 1974 when the unit was put into commercial operation. Since 1974 a number of changes in the regulations and additional requirements have been imposed on operating reactors. The paper traces the influence of the original plant criteria on the backfit evaluations and the minimal physical changes required in the plant's structures and components to comply with the new requirements. In addition, the unique design features and construction challenges of the original design are discussed. Kewaunee Nuclear Power Plant has had one of the best operating performance records in the world. Also, the exposure to radiation for plant personnel and radioactive waste generation has been significantly lower than the average. This has been achieved by a conscientious team effort of all parties involved. Some of the more significant structural design features contributing to the excellent performance is detailed in this paper. (orig.)

SO2 pollution of heavy oil-fired steam power plants in Iran

International Nuclear Information System (INIS)

Nazari, S.; Shahhoseini, O.; Sohrabi-Kashani, A.; Davari, S.; Sahabi, H.; Rezaeian, A.

2012-01-01

Steam power plants using heavy oil provided about 17.4%, equivalent to 35.49 TWh, of electricity in Iran in 2007. However, having 1.55–3.5 weight percentage of sulfur, heavy oil produces SO 2 pollutant. Utilization of Flue Gas Desulfurization systems (FGD) in Iran's steam power plants is not common and thereby, this pollutant is dispersed in the atmosphere easily. In 2007, the average emission factor of SO 2 pollutant for steam power plants was 15.27 g/kWh, which means regarding the amount of electricity generated by steam power plants using heavy oil, 541,000 Mg of this pollutant was produced. In this study, mass distribution of SO 2 in terms of Mg/yr is considered and dispersion of this pollutant in each of the 16 steam power plants under study is modeled using Atmospheric Dispersion Modeling System (ADMS). Details of this study are demonstrated using Geographical Information System (GIS) software, ArcGIS. Finally, the average emission factor of SO 2 and the emission of it in Iran's steam power plants as well as SO 2 emission reduction programs of this country are compared with their alternatives in Turkey and China.

Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

Energy Technology Data Exchange (ETDEWEB)

Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

1986-03-01

This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

International Nuclear Information System (INIS)

Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

1986-03-01

This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants

A human factors data bank for French nuclear power plants

International Nuclear Information System (INIS)

Villemeur, A.; Mosneron-Dupin, F.; Bouissou, M.; Meslin, T.

1986-01-01

CONFUCIUS is a computerized data bank developed by Electricite de France to study human factors in nuclear power plants. A detailed and homogeneous grouping of described operation and maintenance errors as well as of performance times is possible with CONFUCIUS. It also incorporates a selection of statistical treatment softwares. Readily usable and modifiable, the system can easily evolve. It allows a wide range of applications (safety analysis, event analysis, training, human factors engineering, probabilistic analysis). Data derived from the analysis of significant events reported in power plants and from the analysis of simulator tests are used as inputs into this data bank

Industrial safety in power plants

International Nuclear Information System (INIS)

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

NUCLEAR POWER PLANT

Science.gov (United States)

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)

FRESCO, a simplified code for cost analysis of fusion power plants

International Nuclear Information System (INIS)

Bustreo, C.; Casini, G.; Zollino, G.; Bolzonella, T.; Piovan, R.

2013-01-01

Highlights: • FRESCO is a code for rapid evaluation of the cost of electricity of a fusion power plant. • Parameters of the basic machine and unitary costs of components derived from ITER. • Power production components and plant power balance are extrapolated from PPCS. • A special effort is made in the investigation of the pulsed operation scenarios. • Technical and economical FRESCO results are compared with those of two PPCS models. -- Abstract: FRESCO (Fusion REactor Simplified COsts) is a code based on simplified models of physics, engineering and economical aspects of a TOKAMAK-like pulsed or steady-state fusion power plant. The experience coming from various aspects of ITER design, including selection of materials and operating scenarios, is exploited as much as possible. Energy production and plant power balance, including the recirculation requirements, are derived from two models of the PPCS European study, the helium cooled lithium/lead blanket model reactor (model AB) and the helium cooled ceramic one (model B). A detailed study of the availability of the power plant due, among others, to the replacement of plasma facing components, is also included in the code. The economics of the fusion power plant is evaluated through the levelized cost approach. Costs of the basic components are scaled from the corresponding values of the ITER project, the ARIES studies and SCAN model. The costs of plant auxiliaries, including those of the magnetic and electric systems, tritium plants, instrumentation, buildings and thermal energy storage if any, are recovered from ITER values and from those of other power plants. Finally, the PPCS models AB and B are simulated and the main results are reported in this paper

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

Power plants 2010. Lectures

International Nuclear Information System (INIS)

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.

Investigation of organizational structures of nuclear power plants and their cooperation with superordinate organizational structures. Phase 2

International Nuclear Information System (INIS)

1989-01-01

This study gives an overview about the interaction of the German nuclear power industry and other (superior) organisations like supervising agencies, expert organisations and other nuclear power plants, nuclear power plant owners or their associations. The interactions of nuclear power plants with other organisations is partly regulated by law. This is particularly true for the interaction between the nuclear power plants and the supervising agencies respectively the expert organisations. Among one another, the interaction of nuclear power plants is mainly carried out as a voluntary exchange of experience. The task of the study is to analyse the complex patterns of interactions among nuclear power plants and other organisations in detail and to demonstrate the trends of further improvements. Thus, the study does demonstrate the different kinds of interaction between nuclear power plants among another, between nuclear power plants and their supervising agencies and between nuclear power plants and expert organisations. These interactions are evaluated with regard to the existing regulation. (orig.) [de

Reliability of diesel generators in the Finnish and Swedish nuclear power plants

International Nuclear Information System (INIS)

Pulkkinen, U.; Huovinen, T.; Norros, L.; Vanhala, J.

1989-10-01

Diesel generators are used as emergency AC-power sources in nuclear power plants and they produce electric power for other emergency systems during accidents in which offsite power is lost. The reliability of diesel generators is thus of major concern for overall safety of nuclear power plants. In this study we consider the reliability of diesel generators in the Swedish and Finnish nuclear power plants on the basis of collected operational experience. We classify the occurred failures according to their functional criticality, type and cause. The failures caused by human errors in maintenance and testing are analysed in detail. We analyse also the reliability of the diesel generator subsystems. Further, we study the effect of surveillance test and the type of test on the reliability. Finally we construct an unavailability model for single diesel generator unit and discuss the findings of the study giving some practical recommendations

Rock siting of nuclear power plants from a reactor safety standpoint

International Nuclear Information System (INIS)

1975-11-01

The study has aimed at surveying the advantages and disadvantages of a rock sited nuclear power plant from a reactor safety standpoint. The studies performed are almost entirely concentrated on the BWR alternative. The design of a nuclear power plant in rock judged most appropriate has been studied in greater detail, and a relatively extensive safety analysis has been made. It is found that the presented technical design of the rock sited alternative is sufficiently advanced to form a basis for further projecting treatment. The chosen technical design of the reactor plant demands a cavern with a 45-50 metre span. Caverns without strengthening efforts with such spans are used in mines, but have no previously been used for industrial plants. Studies of the stability of such caverns show that a safety level is attainable corresponding to the safety required for the other parts of the nuclear power plant. The conditions are that the rock is of high quality, that necessary strengthening measures are taken and that careful studies of the rock are made before and during the blasting, and also during operation of the plant. When locating a rock sited nuclear power plant, the same criteria must be considered as for an above ground plant, with additional stronger demands for rock quality. The presented rock sited nuclear power plant has been assessed to cost 20 % more in total construction costs than a corresponding above ground plant. The motivations for rock siting also depend on whether a condensing plant for only electricity production, or a plant for combined power production and district heating, is considered. The latter would under certain circumstances make rock siting look more attractive. (author)

The year 2000 power plant

International Nuclear Information System (INIS)

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

Scrubbing system design for CO2 capture in coal-fired power plants

International Nuclear Information System (INIS)

Heischkamp, Elizabeth

2017-01-01

Within the last decades a continuous tightening of environmental regulations has been observed in several countries around the world. These include restriction of anthropogenic CO 2 emissions, since they are considered responsible for intensifying global warming. Coal-fired power plants represent a good possibility for capturing CO 2 before it is emitted in the atmosphere, thereby contributing to combat global warming. This work focuses on reducing the CO 2 emissions of such a power plant by 90 %. For this purpose a hard coal power plant is retrofitted with a chemical absorption using different solutions of piperazine promoted potassium carbonate. The resulting power plant's efficiency losses have been accounted for. A comparison of different scenarios such as the variation of operating parameters offer an insight in detecting suitable operating conditions that will allow to minimize efficiency penalties. Simulation details are provided along with a technical and an economic analysis.

Estimation of environmental external costs between coal fired power plant and nuclear power plant

International Nuclear Information System (INIS)

Moon, G. H.; Kim, S. S.

2000-01-01

First of all, this study evaluated the impacts on the health and the environment of air pollutants emitted from coal power plant and nuclear power pant, two major electric power generating options in Korea. Then, the environmental external costs of those two options were estimated by transforming the health and environment impact into monetary values. To do this, AIRPACTS and Impacts of Atmospheric Release model developed by IAEA were used. The environmental external cost of Samcheonpo coal power plant was estimated about 25 times as much as that of Younggwang nuclear power plant. This result implies that nuclear power plant is a clean technology compared with coal power plant. This study suggests that the external cost should be reflected in the electric system expansion plan in order to allocate energy resources efficiently and to reduce economic impact stemming from the environmental regulation emerged recently on a global level

Organization patterns of PWR power plants

International Nuclear Information System (INIS)

Leicman, J.

1980-01-01

Organization patterns are shown for the St. Lucia 1, North Anna, Sequoyah, and Beaver Valley nuclear power plants, for a typical PWR power plant in the USA, for the Biblis/RWE-KWU nuclear power plants and for a four-unit nuclear power plant operated by Electricite de France as well as for the Loviisa power plant. Organization patterns are also shown for relatively independent and non-independent nuclear power plants according to IAEA recommendations. (J.P.)

Nuclear power plant siting

International Nuclear Information System (INIS)

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.)

Test and maintenance of the emergency power supply in the nuclear power plant Biblis

International Nuclear Information System (INIS)

Kotthoff, K.; Huren, H.

1986-01-01

Besides design and construction test and maintenance play an important role for the availability of the emergency power supply. As an example test and maintenance provided for the emergency power supply in a German 4-loop PWR will be described. In general one has to differentiate between test and maintenance performed during power operation of the plant and those carried out during the refuelling outage. For both periods of operation detailed information will be given including type, extent and frequency of test and maintenance work. The results of test and maintenance up to now will be discussed. (authors)

Test and maintenance of the emergency power supply in the nuclear power plant Biblis

Energy Technology Data Exchange (ETDEWEB)

Kotthoff, K. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany); Huren, H. [Rheinisch-Westfaelisches Elektrizitaetswerk AG, Betriebsverwaltung Biblis, Biblis (Germany)

1986-02-15

Besides design and construction test and maintenance play an important role for the availability of the emergency power supply. As an example test and maintenance provided for the emergency power supply in a German 4-loop PWR will be described. In general one has to differentiate between test and maintenance performed during power operation of the plant and those carried out during the refuelling outage. For both periods of operation detailed information will be given including type, extent and frequency of test and maintenance work. The results of test and maintenance up to now will be discussed. (authors)

Lifetime management research trend of Kori-1 nuclear power plant

International Nuclear Information System (INIS)

Kim, J. S.; Jeong, I. S.; Hong, S. Y.

1998-01-01

KEPRI launched the Nuclear Power Plant Lifetime Management Study(II) for the management of the latter half life of Kori-1. Main goal of LCM-IV study is the detail evaluation of main equipment life and establishment of aging management based on LCM-IV result. The result of LCM-IV on the kori-1 confirmed the technical and economical feasibility of life extension beyond the design life. Owing to absence of The regulatory policy for the life extension in korea, LCM-IV will focus on the minimum study which is essential for the actual lifetime management for the old nuclear power plant. License renewal study is expected after the establishment of Regulatory policy about the life extension of nuclear power plant. LCM trend in korea and abroad, result of technical and economical feasibility study and summary of LCM-IV is described on this paper

Exergoeconomic evaluation of a KRW-based IGCC power plant

International Nuclear Information System (INIS)

Tsatsavonis, G.; Lin, L.; TawFik, T.; Gallaspy, D.T.

1991-01-01

This paper reports on a study supported by the US Department of Energy, in which several design configurations of Kellogg-Rust-Westinghouse (KRW)-based Integrated Gasification-Combined-Cycle (IGCC) power plants were developed. One of these configurations was analyzed from the exergoeconomic (thermoeconomic) viewpoint. The detailed exergoeconomic evaluation identified several changes for improving the cost effectiveness of this IGCC design configuration. Based on the cost information supplied by the M.W. Kellogg Company, an attempt was made to calculate the economically optimal exergetic efficiency for some of the most important plant components. This information is currently used in plant optimization studies

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

International Nuclear Information System (INIS)

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

Piping engineering for nuclear power plant

International Nuclear Information System (INIS)

Curto, N.; Schmidt, H.; Muller, R.

1988-01-01

In order to develop piping engineering, an adequate dimensioning and correct selection of materials must be secured. A correct selection of materials together with calculations and stress analysis must be carried out with a view to minimizing or avoiding possible failures or damages in piping assembling, which could be caused by internal pressure, weight, temperature, oscillation, etc. The piping project for a nuclear power plant is divided into the following three phases. Phase I: Basic piping design. Phase II: Final piping design. Phase III: Detail engineering. (Author)

Wind power plant system services

DEFF Research Database (Denmark)

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...

Radionuclide emissions from a coal-fired power plant

International Nuclear Information System (INIS)

Amin, Y.M.; Uddin Khandaker, Mayeen; Shyen, A.K.S.; Mahat, R.H.; Nor, R.M.; Bradley, D.A.

2013-01-01

Current study concerns measurement of radioactivity levels in areas surrounding a 2420 MW thermal power plant fueled predominantly by bituminous coal. The concentrations of 226 Ra, 232 Th and 40 K in onsite bottom-ash were found to be 139 Bq/kg, 108 Bq/kg and 291 Bq/kg, respectively, the levels for these radiolnuclides in soil decreasing with distance from the power plant. At the plant perimeter the respective radionuclide concentrations were 87 Bq/kg, 74 Bq/kg and 297 Bq/kg. In a nearby town, the corresponding concentrations were 104 Bq/kg, 52 Bq/kg and 358 Bq/kg, suggestive of use of TENORM affected soils. The mean radium equivalent activities (Ra eq ) in soil and ash sample in the town were 205 Bq/kg and 316 Bq/kg, respectively. The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste. For the prevailing levels of exposure and a worst case senario, the predicted committed effective dose due to ingestion and inhalation for intake durations of 1- and 30 years would be 4.2 μSv and 220 μSv, respectively. - Highlights: • Detailed studies on naturally occuring radionuclide emissions due to a 2420 MW coal-fired power plant in Malaysia. • Assessment of radiation exposures to the public around the power plant due to an intake of the radionuclides. • The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. • The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste

The economy of Baden-Wuerttemberg needs more nuclear power plants

International Nuclear Information System (INIS)

Anon.

1982-01-01

In a detailed comment the working group of the twelve Chambers of Industry and Commerce of Baden-Wuerttemberg at Stuttgart has presented the economic consequences of delays in nuclear power plant expansion and made claims on energy policy which are derived from these consequences. (orig.) [de

Internal exposure in French nuclear power plants : 10 years on

International Nuclear Information System (INIS)

Chevalier, C.; Gonin, M.

1992-01-01

Collectively speaking, internal exposure in French nuclear power plants is negligible. However, some quite high individual doses have been recorded. The details of cases of significant contamination are presented here in table form. A brief discussion of a few particular cases underscores the problems involved. (author)

Towards retrofitting integrated gasification combined cycle (IGCC) power plants with solid oxide fuel cells (SOFC) and CO

NARCIS (Netherlands)

Thallam Thattai, A.; Oldenbroek, V.D.W.M.; Schoenmakers, L; Woudstra, T.; Purushothaman Vellayani, A.

2017-01-01

This article presents a detailed thermodynamic case study based on the Willem-Alexander Centrale (WAC) power plant in the Netherlands towards retrofitting SOFCs in existing IGCC power plants with a focus on near future implementation. Two systems with high percentage (up to 70%) biomass

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

DEFF Research Database (Denmark)

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...

Images of nuclear power plants

International Nuclear Information System (INIS)

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.)

On nuclear power plant uprating

International Nuclear Information System (INIS)

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)

Performance assessment of non-self-regulating controllers in a cogeneration power plant

International Nuclear Information System (INIS)

Howard, Rachelle; Cooper, Douglas J.

2009-01-01

This work details a novel method for assessing the performance of a PI (proportional-integral) feedback controller when the process displays non-self-regulating dynamic behavior. By applying an intuitive process control-based pattern recognition method to the autocorrelation function of the process measurement signal, the controller's disturbance rejection performance can automatically be categorized. Stochastic data collected over days or weeks is analyzed to compute an index descriptive of current controller performance. If the control response has drifted from a user-defined target value, the analysis further provides a guide for tuning adjustments to restore desired performance. Significant aspects of this approach are that no plant disruption or process knowledge is required for evaluation. Classic examples of non-self-regulating behavior include certain liquid level control loops and pressure control loops which are prevalent in cogeneration power plants. In this work, we detail how the performance assessment method was used to improve performance of such controllers in the University of Connecticut's power plant.

Small hydroelectric power plants

International Nuclear Information System (INIS)

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

The Kuroshio power plant

CERN Document Server

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

Conceptual engineering design study of thermionic topping of fossil power plants

Energy Technology Data Exchange (ETDEWEB)

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.

Hydrogeological modelling of the eastern region of Areco river locally detailed on Atucha I and II nuclear power plants area

International Nuclear Information System (INIS)

Grattone, Natalia I.; Fuentes, Nestor O.

2009-01-01

Water flow behaviour of Pampeano aquifer was modeled using Visual Mod-flow software Package 2.8.1 with the assumption of a free aquifer, within the region of the Areco river and extending to the rivers of 'Canada Honda' and 'de la Cruz'. Steady state regime was simulated and grid refinement allows obtaining locally detailed calculation in the area of Atucha I and II Nuclear power plants, in order to compute unsteady situations as the consequence of water flow variations from and to the aquifer, enabling the model to study the movement of possible contaminant particles in the hydrogeologic system. In this work the effects of rivers action, the recharge conditions and the flow lines are analyzed, taking always into account the range of reliability of obtained results, considering the incidence of uncertainties introduced by data input system, the estimates and interpolation of parameters used. (author)

Fuel handling and storage systems in nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

The scope of this Guide includes the design of handling and storage facilities for fuel assemblies from the receipt of fuel into the nuclear power plant until the fuel departs from that plant. The unirradiated fuel considered in this Guide is assumed not to exhibit any significant level of radiation so that it can be handled without shielding or cooling. This Guide also gives limited consideration to the handling and storage of certain core components. While the general design and safety principles are discussed in Section 2 of this Guide, more specific design requirements for the handling and storage of fuel are given in detailed sections which follow the general design and safety principles. Further useful information is to be found in the IAEA Technical Reports Series No. 189 ''Storage, Handling and Movement of Fuel and Related Components at Nuclear Power Plants'' and No. 198 ''Guide to the Safe Handling of Radioactive Wastes at Nuclear Power Plants''. However, the scope of the Guide does not include consideration of the following: (1) The various reactor physics questions associated with fuel and absorber loading and unloading into the core; (2) The design aspects of preparation of the reactor for fuel loading (such as the removal of the pressure vessel head for a light water reactor) and restoration after loading; (3) The design of shipping casks; (4) Fuel storage of a long-term nature exceeding the design lifetime of the nuclear power plant; (5) Unirradiated fuel containing plutonium

Plant life management optimized utilization of existing nuclear power plants

International Nuclear Information System (INIS)

Watzinger, H.; Erve, M.

1999-01-01

For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

Reliability methods in nuclear power plant ageing management

International Nuclear Information System (INIS)

Simola, K.

1999-01-01

The aim of nuclear power plant ageing management is to maintain an adequate safety level throughout the lifetime of the plant. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time-dependent degradation. The phases of ageing analyses are generally the identification of critical components, identification and evaluation of ageing effects, and development of mitigation methods. This thesis focuses on the use of reliability methods and analyses of plant- specific operating experience in nuclear power plant ageing studies. The presented applications and method development have been related to nuclear power plants, but many of the approaches can also be applied outside the nuclear industry. The thesis consists of a summary and seven publications. The summary provides an overview of ageing management and discusses the role of reliability methods in ageing analyses. In the publications, practical applications and method development are described in more detail. The application areas at component and system level are motor-operated valves and protection automation systems, for which experience-based ageing analyses have been demonstrated. Furthermore, Bayesian ageing models for repairable components have been developed, and the management of ageing by improving maintenance practices is discussed. Recommendations for improvement of plant information management in order to facilitate ageing analyses are also given. The evaluation and mitigation of ageing effects on structural components is addressed by promoting the use of probabilistic modelling of crack growth, and developing models for evaluation of the reliability of inspection results. (orig.)

Reliability methods in nuclear power plant ageing management

Energy Technology Data Exchange (ETDEWEB)

Simola, K. [VTT Automation, Espoo (Finland). Industrial Automation

1999-07-01

The aim of nuclear power plant ageing management is to maintain an adequate safety level throughout the lifetime of the plant. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time-dependent degradation. The phases of ageing analyses are generally the identification of critical components, identification and evaluation of ageing effects, and development of mitigation methods. This thesis focuses on the use of reliability methods and analyses of plant- specific operating experience in nuclear power plant ageing studies. The presented applications and method development have been related to nuclear power plants, but many of the approaches can also be applied outside the nuclear industry. The thesis consists of a summary and seven publications. The summary provides an overview of ageing management and discusses the role of reliability methods in ageing analyses. In the publications, practical applications and method development are described in more detail. The application areas at component and system level are motor-operated valves and protection automation systems, for which experience-based ageing analyses have been demonstrated. Furthermore, Bayesian ageing models for repairable components have been developed, and the management of ageing by improving maintenance practices is discussed. Recommendations for improvement of plant information management in order to facilitate ageing analyses are also given. The evaluation and mitigation of ageing effects on structural components is addressed by promoting the use of probabilistic modelling of crack growth, and developing models for evaluation of the reliability of inspection results. (orig.)

Some power uprate issues in nuclear power plants

International Nuclear Information System (INIS)

Tipping, Philip

2008-01-01

Issues and themes concerned with nuclear power plant uprating are examined. Attention is brought to the fact that many candidate nuclear power plants for uprating have anyway been operated below their rated power for a significant part of their operating life. The key issues remain safety and reliability in operation at all times, irrespective of the nuclear power plant's chronological or design age or power rating. The effects of power uprates are discussed in terms of material aspects and expected demands on the systems, structures and components. The impact on operation and maintenance methods is indicated in terms of changes to the ageing surveillance programmes. Attention is brought to the necessity checking or revising operator actions after power up-rating has been implemented

Technology success: Integration of power plant reliability and effective maintenance

International Nuclear Information System (INIS)

Ferguson, K.

2008-01-01

The nuclear power generation sector has a tradition of utilizing technology as a key attribute for advancement. Companies that own, manage, and operate nuclear power plants can be expected to continue to rely on technology as a vital element of success. Inherent with the operations of the nuclear power industry in many parts of the world is the close connection between efficiency of power plant operations and successful business survival. The relationship among power plant availability, reliability of systems and components, and viability of the enterprise is more evident than ever. Technology decisions need to be accomplished that reflect business strategies, work processes, as well as needs of stakeholders and authorities. Such rigor is needed to address overarching concerns such as power plant life extension and license renewal, new plant orders, outage management, plant safety, inventory management etc. Particular to power plant reliability, the prudent leveraging of technology as a key to future success is vital. A dominant concern is effective asset management as physical plant assets age. Many plants are in, or are entering in, a situation in which systems and component design life and margins are converging such that failure threats can come into play with increasing frequency. Wisely selected technologies can be vital to the identification of emerging threats to reliable performance of key plant features and initiating effective maintenance actions and investments that can sustain or enhance current reliability in a cost effective manner. This attention to detail is vital to investment in new plants as well This paper and presentation will address (1) specific technology success in place at power plants, including nuclear, that integrates attention to attaining high plant reliability and effective maintenance actions as well as (2) complimentary actions that maximize technology success. In addition, the range of benefits that accrue as a result of

Offshore atomic power plants

International Nuclear Information System (INIS)

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.)

Benchmarking Nuclear Power Plants

International Nuclear Information System (INIS)

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).

The commissioning of nuclear power plants

International Nuclear Information System (INIS)

1989-09-01

The objectives and requirements to be met in commissioning nuclear power plants are presented. The objective of commissioning is to ensure that each component, subsystem, system, or structure in a plant will be capable of fulfilling its design requirements throughout its design life. The requirements for commissioning are: the preparation of a detailed, comprehensive, documented program to demonstrate that all components, systems and structures relevant to safety meet design intent; documented evidence that safety systems are fully operable and can meet design requirements; and, appropriate documentation of the actual state or behaviour of all components, systems and structures relevant to safety. All systems must be included in the commissioning program. Whenever possible, full safety system test should be performed. If a full system in situ test is not possible, alternative means are suggested. (8 refs.)

Planning and management of outages in nuclear power plants

International Nuclear Information System (INIS)

Sica, G.F.; Fusari, W.; Reginelli, A.

1984-01-01

At present the Ente Nazionale per l'Energia Elettrica (ENEL) operates three nuclear power plants, only one of which belongs to the new generation, i.e. the Caorso Nuclear Power Plant which has been in commercial operation since December 1981. Outage planning, implementation and analysis are very important in order to minimize the shutdown time and thus improve plant availability, which is of particular importance for a large nuclear power plant. Such activities are very complicated because of the large number of jobs that have to be performed in accordance with detailed written procedures and which have to be properly documented and controlled. Large off-site resources are required which have to be accurately interfaced with on-site staff. The ENEL is making a great effort to define both the administrative and technical aspects of refuelling outages. As outage planning requires the availability and handling of a large amount of data and information, a maintenance information system that has been widely used in conventional plants was applied, with some modifications made especially for the Caorso Nuclear Power Plant. After two years the following results have been achieved: a large number of raw and processed data are now available, the first refuelling outage was carried out with few problems and according to schedule, and the second refuelling outage, based on the experience of the first, required somewhat less preparation and is developing well even though many special activities have had to be scheduled. The ENEL believes that the efforts made in the planning and management areas will pay off in terms of the short duration, smoothness and economy of further outages, both for Caorso and for future plants. (author)

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Hybrid combined cycle power plant

International Nuclear Information System (INIS)

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)

Use of waste heat from nuclear power plants

International Nuclear Information System (INIS)

Olszewski, M.

1978-01-01

The paper details the Department of Energy (DOE) program concerning utilization of power plant reject heat conducted by the Oak Ridge National Laboratory (ORNL). A brief description of the historical development of the program is given and results of recent studies are outlined to indicate the scope of present efforts. A description of a DOE-sponsored project assessing uses for reject heat from the Vermont Yankee Nuclear Station is also given

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2003-01-01

This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

Nuclear Power Plants. Construction status report, data as of February 28, 1978

International Nuclear Information System (INIS)

1978-03-01

Data on the construction status of nuclear power plants in the US as of February 28, 1978 are presented. The data include licensing activities affecting the construction as well as detailed information on construction activities and schedules

Feasibility of Hybrid Retrofits to Off-Grid Diesel Power Plants in the Philippines

International Nuclear Information System (INIS)

Abergas, R.L.; Barley, C.D.; Barruela, R.B.

1999-01-01

The Strategic Power Utilities Group (SPUG) of the National Power Corporation (NPC) in the Philippines owns and operates about 100 power plants, mostly fueled by diesel, ranging in energy production from about 15 kilowatt-hours (kWh)/day to 106,000 kWh/day. Reducing the consumption of diesel fuel in these plants, along with the associated financial losses, is a priority for SPUG. The purpose of this study is to estimate the potential fuel and cost savings that might be achieved by retrofitting hybrid power systems to these existing diesel plants. As used in this report, the term ''hybrid system'' refers to any combination of wind turbine generators (WTGs), photovoltaic (PV) modules, lead-acid batteries, and an AC/DC power converter (either an electronic inverter or a rotary converter), in addition to the existing diesel gensets. The resources available for this study did not permit a detailed design analysis for each of the plants. Instead, the following five-step process was used: 1.Tabulate some important characteristics of all the plants. 2.Group the plants into categories (six classes) with similar characteristics. 3.For each class of system, identify one plant that is representative of the class. 4.For each representative plant, perform a moderately detailed prefeasibility analysis of design options. 5.Summarize and interpret the results. The analysis of each representative plant involved the use of time-series computer simulation models to estimate the fuel usage, maintenance expenses, and cash flow resulting from various designs, and to search the domain of possible designs for the one leading to the lowest life-cycle cost. Cost items that would be unaffected by the retrofit, such as operator salaries and the capital cost of existing equipment, were not included in the analysis. Thus, the results are reported as levelized cost of energy (COE) savings: the difference between the cost of the existing diesel-only system and that of an optimized hybrid system

Power generation by nuclear power plants

International Nuclear Information System (INIS)

Bacher, P.

2004-01-01

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

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2000-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Developmental trends on nuclear power plants in the world'. In this report, some data at the end of 1999 was made up on bases of answers on questionnaires from 72 electric companies in 31 nations and regions in the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; location of the plants; the plants in the world; and so forth. And, it also has some survey results on the 'Liberalization of electric power markets and nuclear power generation' such as some 70% of respondents in nuclear power for future option, gas-thermal power seen as power source with most to gain from liberalization, merits on nuclear power generation (environmental considerations and supply stability), most commonly voiced concern about new plant orders in poor economy, and so forth. (G.K.)

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Power Prediction and Technoeconomic Analysis of a Solar PV Power Plant by MLP-ABC and COMFAR III, considering Cloudy Weather Conditions

Directory of Open Access Journals (Sweden)

M. Khademi

2016-01-01

Full Text Available The prediction of power generated by photovoltaic (PV panels in different climates is of great importance. The aim of this paper is to predict the output power of a 3.2 kW PV power plant using the MLP-ABC (multilayer perceptron-artificial bee colony algorithm. Experimental data (ambient temperature, solar radiation, and relative humidity was gathered at five-minute intervals from Tehran University’s PV Power Plant from September 22nd, 2012, to January 14th, 2013. Following data validation, 10665 data sets, equivalent to 35 days, were used in the analysis. The output power was predicted using the MLP-ABC algorithm with the mean absolute percentage error (MAPE, the mean bias error (MBE, and correlation coefficient (R2, of 3.7, 3.1, and 94.7%, respectively. The optimized configuration of the network consisted of two hidden layers. The first layer had four neurons and the second had two neurons. A detailed economic analysis is also presented for sunny and cloudy weather conditions using COMFAR III software. A detailed cost analysis indicated that the total investment’s payback period would be 3.83 years in sunny periods and 4.08 years in cloudy periods. The results showed that the solar PV power plant is feasible from an economic point of view in both cloudy and sunny weather conditions.

Nuclear power plants. Construction status report, data as of April 30, 1978

International Nuclear Information System (INIS)

1978-05-01

Data on the construction status of nuclear power plants in the U.S. as of April 30, 1978 are presented. The data include licensing activities affecting the construction as well as detailed information on construction activities and schedules

Life time of nuclear power plants and new types of reactors

International Nuclear Information System (INIS)

2003-05-01

This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

Perspectives of nuclear power plants

International Nuclear Information System (INIS)

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.)

Pumped storage power plants in Denmark. Pumpekraftvaerker i Danmark

Energy Technology Data Exchange (ETDEWEB)

1988-12-15

In 1988 there are about 250 pumped storage power plants throughout the world, yet it is difficult to obtain data about them. They are usually situated in mountainous areas so that great differences in height can be obtained between the upper and lower water storage facilities. These plants consist of the power system (turbines, pumps, generators, motors, etc.) natural or artificial water storage facilities, and water routes, (in and outgoing constructions, pressure pipes, etc.). In Denmark, reversible pumping turbines are preferred, and here specific Danish products are examined (62.5MW and a 125 MW). Possible designs for water storage basins are analyzed in detail, also with regard to their comparative economic advantages. It has been considered reasonable to site this kind of power plant in Danish coastal regions, this would be the first case where the sea has been used for the lower water storage basin. Possible sites in Jutland and on the island of Als have been investigated. In a basin for a 250 MW pumped storage power plant with optimal production throughout 8 hours, a siting 60 m above sea level could cover power production for an area of about 100 hectars. Material for a dam surrounding the lower water storage system could be produced when digging out the basin. The dam should be about 20m higher than the surrounding terrain and the volume would be about 3,2 mio. m/sup 3/. The filled basin would contain 14.0 mio. m/sup 3/ water. The velocity and volume of outgoing water masses would be very considerable and would exact safety precautions to protect ships and bathers. A tentative cost benefit analysis is presented which indicates that the possible establishment of this type of power plant in Denmark could be of considerable interest. (AB). 15 refs.

Advanced targeted monitoring of high temperature components in power plants

Energy Technology Data Exchange (ETDEWEB)

Roos, E; Maile, K; Jovanovic, A [MPA Stuttgart (Germany)

1999-12-31

The article presents the idea of targeted monitoring of high-temperature pressurized components in fossil-fueled power plants, implemented within a modular software system and using, in addition to pressure and temperature data, also displacement and strain measurement data. The concept has been implemented as a part of a more complex company-oriented Internet/Intranet system of MPA Stuttgart (ALIAS). ALIAS enables to combine smoothly the monitoring results with those of the off-line analysis, e. g. sensitivity analyses, comparison with preceding experience (case studies), literature search, search in material databases -(experimental and standard data), nonlinear FE-analysis, etc. The concept and the system have been implemented in real plant conditions several power plants in Germany and Europe: one of these applications and its results are described more in detail in the presentation. (orig.) 9 refs.

Advanced targeted monitoring of high temperature components in power plants

Energy Technology Data Exchange (ETDEWEB)

Roos, E.; Maile, K.; Jovanovic, A. [MPA Stuttgart (Germany)

1998-12-31

The article presents the idea of targeted monitoring of high-temperature pressurized components in fossil-fueled power plants, implemented within a modular software system and using, in addition to pressure and temperature data, also displacement and strain measurement data. The concept has been implemented as a part of a more complex company-oriented Internet/Intranet system of MPA Stuttgart (ALIAS). ALIAS enables to combine smoothly the monitoring results with those of the off-line analysis, e. g. sensitivity analyses, comparison with preceding experience (case studies), literature search, search in material databases -(experimental and standard data), nonlinear FE-analysis, etc. The concept and the system have been implemented in real plant conditions several power plants in Germany and Europe: one of these applications and its results are described more in detail in the presentation. (orig.) 9 refs.

Problems of power plant capital demands

International Nuclear Information System (INIS)

Slechta, V.; Bohal, L.

1986-01-01

The problems are discussed of requirements for investment for power plants in Czechoslovakia. Since the construction was finished of coal-burning 110 MW power plants with six power units, specific capital cost has steadily been growing. The growth amounts to 6 to 8% per year while the principle has been observed that specific capital cost decreases with increased unit power. Attention is paid to the cost of the subcontractors of the building and technological parts of a power plant and to the development of productivity of labour. A comparison is tabulated of cost for coal-burning power plants with 100 MW and 200 MW units and for nuclear power plants with WWER-440 reactors. Steps are suggested leading to a reduction of the capital cost of nuclear power plants. It is stated that should not these steps be taken, the envisaged development of nuclear power would be unbearable for the Czechoslovak national economy. (Z.M.). 8 tabs., 3 refs

Evaluation of fire hazard analyses for nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1995-01-01

The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire safety of nuclear power plants. The publication supplements the broad concepts of Safety Series No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, by providing a detailed list of the issues, and some of the limitations, to be considered when evaluating the adequacy and effectiveness of the fire hazard analysis of a nuclear power plant. The publication is intended for assessors of fire hazard analyses, including regulators, independent assessors or plant assessors, and gives a broad description of the methodology to be used by operators in preparing a fire hazard analysis for their own plant. 1 fig

Nuclear power plant diagnostic system

International Nuclear Information System (INIS)

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.)

Next Generation Geothermal Power Plants

Energy Technology Data Exchange (ETDEWEB)

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

Power plant chemical technology

Energy Technology Data Exchange (ETDEWEB)

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)

Transient evaluation using EMTP at single open phase with the offsite power transformer for the emergency power supply systems of nuclear power plants

International Nuclear Information System (INIS)

Shimada, Yoshio

2017-01-01

The emergency power supply systems of nuclear power plants, as the objects of this research, are critical in supplying stable electric power to such systems as the emergency core cooling system (ECCS), and in maintaining safety of the nuclear power reactor; this was apparent in the accident at the Fukushima Daiichi Nuclear Power Station. The Nuclear Regulatory Commission (USNRC) issued regulatory documents (BL 2012-011, IN 2012-032), and has commenced evaluations on newly discovered vulnerability in the design of power supply systems which cannot be detected with under-voltage protection relays, with certain kinds of configuration of coils and iron core structures, such as when the offsite power supply side is a Y-connection and the load side is a ⊿-connection etc., when the detection of single open phase fault with the circuit of a transformer which is without a ground fault connected to the offsite power supply system. This report uses simulation by the electro magnetic transients program (EMTP) and clearly describe the response at the time of the power supply single open phase without ground fault for various configuration of coils and various iron core structures of the three-phase transformer, and identify the important issues in the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the single open phase fault occurred without ground fault. This report describes the results of the simulations of operations of the protection relays of the emergency power supply systems and the safety related components of representative a domestic PWR plant with EMTP. This report explains the method to detect open-phase when the transformer is no-load which United States Electric Power Research Institute (EPRI) developed. As the detailed analyses data from EPRI related to the detection method concerned have not been disclosed officially yet, in this paper, the quantitative and detailed verification results

Nuclear power plants in populated areas

International Nuclear Information System (INIS)

Wachsmann, F.

1973-01-01

The article first deals with the permanently increasing demand for electical power. Considering the ever growing energy demand which can no longer be covered by conventional power plants, it has become necessary to set up nuclear power plants of larger range. The author presents in a survey the basic function of nuclear power plants as well as the resulting risks and safety measures. The author concludes that according to present knowledge there is no more need to erect nuclear power plants outside densely populated urban areas but there is now the possibility of erecting nuclear power plants in densely populated areas. (orig./LH) [de

Technical guidelines for aseismic design of nuclear power plants

International Nuclear Information System (INIS)

Park, Y.J.; Hofmayer, C.H.

1994-06-01

This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

Improving the safety of LWR power plants. Final report

International Nuclear Information System (INIS)

1980-04-01

This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs

Nuclear power plant decommissioning

International Nuclear Information System (INIS)

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)

Scrubbing system design for CO{sub 2} capture in coal-fired power plants

Energy Technology Data Exchange (ETDEWEB)

Heischkamp, Elizabeth

2017-07-01

Within the last decades a continuous tightening of environmental regulations has been observed in several countries around the world. These include restriction of anthropogenic CO{sub 2} emissions, since they are considered responsible for intensifying global warming. Coal-fired power plants represent a good possibility for capturing CO{sub 2} before it is emitted in the atmosphere, thereby contributing to combat global warming. This work focuses on reducing the CO{sub 2} emissions of such a power plant by 90 %. For this purpose a hard coal power plant is retrofitted with a chemical absorption using different solutions of piperazine promoted potassium carbonate. The resulting power plant's efficiency losses have been accounted for. A comparison of different scenarios such as the variation of operating parameters offer an insight in detecting suitable operating conditions that will allow to minimize efficiency penalties. Simulation details are provided along with a technical and an economic analysis.

The end of cheap electric power from nuclear power plants. 2. ed.

International Nuclear Information System (INIS)

Franke, J.; Viefhues, D.

1984-04-01

The economic efficiency of a nuclear power plant is compared with that of a coal-fired power plant of the same size. A technical and economic computer model was developed which took account of the power plant and all its units as well as the fuel cycle (including intermediate storage and reprocessing). It was found that future nuclear power plants will be inferior to coal-fired power plants in all economic respects. Further, there was no load range in which the cost of electric power generation was more favourable in nuclear power plants than in coal-fired power plants. (orig./HSCH) [de

Managed maintenance, the next step in power plant maintenance

International Nuclear Information System (INIS)

Butterworth, G.; Anderson, T.M.

1984-01-01

The Westinghouse Nuclear Services Integration Division managed maintenance services are described. Essential to the management and control of a total plant maintenance programme is the development of a comprehensive maintenance specification. During recent years Westinghouse has jointly developed total plant engineering-based maintenance specifications with a number of utilities. The process employed and the experience to date are described. To efficiently implement the maintenance programme Westinghouse has developed a computer software program specifically designed for day to day use at the power plant by maintenance personnel. This program retains an equipment maintenance history, schedules maintenance activities, issues work orders and performs a number of sophisticated analyses of the maintenance backlog and forecast, equipment failure rates, etc. The functions of this software program are described and details of Westinghouse efforts to support the utilities in reducing outage times through development of predefined outage plans for critical report maintenance activities are given. Also described is the experience gained in the training of specialized maintenance personnel, employing competency-based training techniques and equipment mock-ups, and the benefits experienced, in terms of improved quality and productivity of maintenance performed. The success experienced with these methods has caused Westinghouse to expand the use of these training techniques to the more routine skill areas of power plant maintenance. A significant reduction in the operating costs of nuclear power plants will only be brought about by a significant improvement in the quality of maintenance. Westinghouse intends to effect this change by expanding its international service capabilities and to make major investments in order to promote technological developments in the area of power plant maintenance. (author)

Study on modular technology based on the reference nuclear power plant

International Nuclear Information System (INIS)

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)

Survey of thermal-hydraulic models of commercial nuclear power plants

International Nuclear Information System (INIS)

Determan, J.C.; Hendrix, C.E.

1992-12-01

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described

Guidance for emergency planning in nuclear power plants

International Nuclear Information System (INIS)

Magnusson, Tommy; Ekdahl, Maria

2008-06-01

Ringhals has been a model for this study, but the purpose has been to make the report applicable at all nuclear power plants in Sweden. The work has been done in close co-operation with the Swedish nuclear power plants and Rescue Services in the nuclear power municipalities Oesthammar, Oskarshamn, and Varberg. The internal fire brigade at the nuclear power plants has also been involved. A document will also be published as a further guidance at efforts of the type fires, which are mentioned in the enclosed document. After a fire in a switchgear room in 2005 the need of making the existing effort planning more effective at nuclear power plants was observed. The idea with the planning is to plan the effort in order to give the operational and emergency staff a good and actual support to come to a decision and to start the mission without delay. The risk information is showed by planning layouts, symbols and drawings as basis, give risk information and effort information. The effort information shows outer arrangements, manual action points, fire installations, passive fire safety etc. The risk information is shown by risk symbols. Their purpose is to give a fast overview of the existing risks. Reactor safety effects is the ruling influence if an effort has to be done in order to secure safety for a third person. In order to make an effort in an area personal risks for rescue staff, such as electricity risks, radiological risks, chemicals and gas bottles with compressed gases, has to be eliminated. For complicated missions detailed instructions are needed in order to handle specific risks. In a group discussion different people with pertinent knowledge has to value which problematic efforts need detailed instruction. Missions that have to be analyzed in a work group as above are: fire may affect the reactor safety, fire that may threaten the structural integrity, chemical discharge with big consequence on environment/third person and handling of gas system (compressed

Financing of nuclear power plant using resources of power generation

International Nuclear Information System (INIS)

Slechta, V.; Milackova, H.

1987-01-01

It is proved that during the lifetime of a power plant, financial resources are produced from depreciation and from the profit for the delivered electrical power in an amount allowing to meet the cost of construction, interests of credits, the corporation taxes, and the means usable by the utility for simple reproduction of the power plant, additional investment, or for the ultimate decommissioning of the nuclear power plant. The considerations are simplified to 1 MW of installed capacity of a WWER-440 nuclear power plant. The breakdown is shown of the profit and the depreciation over the power plant lifetime, the resources of regular payments of credit instalments for the construction and the method of its calculation, and the income for the state budget and for the utility during the plant liofetime. (J.B.). 5 tabs., 5 refs

Nuclear Power Plants (Rev.)

Energy Technology Data Exchange (ETDEWEB)

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.

Design Provisions for Station Blackout at Nuclear Power Plants

International Nuclear Information System (INIS)

Duchac, Alexander

2015-01-01

A station blackout (SBO) is generally known as 'a plant condition with complete loss of all alternating current (AC) power from off-site sources, from the main generator and from standby AC power sources important to safety to the essential and nonessential switchgear buses. Direct current (DC) power supplies and un-interruptible AC power supplies may be available as long as batteries can supply the loads. Alternate AC power supplies are available'. A draft Safety Guide DS 430 'Design of Electrical Power Systems for Nuclear Power Plants' provides recommendations regarding the implementation of Specific Safety Requirements: Design: Requirement 68 for emergency power systems. The Safety Guide outlines several design measures which are possible as a means of increasing the capability of the electrical power systems to cope with a station blackout, without providing detailed implementation guidance. A committee of international experts and advisors from numerous countries is currently working on an IAEA Technical Document (TECDOC) whose objective is to provide a common international technical basis from which the various criteria for SBO events need to be established, to support operation under design basis and design extension conditions (DEC) at nuclear power plants, to document in a comprehensive manner, all relevant aspects of SBO events at NPPs, and to outline critical issues which reflect the lessons learned from the Fukushima Dai-ichi accident. This paper discusses the commonly encountered difficulties associated with establishing the SBO criteria, shares the best practices, and current strategies used in the design and implementation of SBO provisions and outline the structure of the IAEA's SBO TECDOC under development. (author)

Modernisation for maintaining and improving safety at Nordic nuclear power plants

International Nuclear Information System (INIS)

Hammer, L.; Wahlstroem, B.; Simola, K.

1998-02-01

The safety practices in Finland and Sweden are described and compared in regard of effecting modernisation for safety of the nuclear plants in the two countries, considering new technology and advancing safety requirements as proposed for new reactors. Particular attention is given to strategies for applying new safety requirements to reactors built to earlier standards, and to the interplay between the nuclear utilities and the safety authorities. Overviews are given of past and current modernisation of the nuclear power plants in Finland and Sweden. The management procedures in controlling the implementation of modifications to the nuclear power plants are described and discussed in regard of prevailing differences between Finnish and Swedish practices. A formal modelling technique (SADT) was applied for capture of the essential contents of the relevant documented procedures. Two examples of recent plant modifications in the Finnish nuclear plants in Olkiluoto and Loviisa are described and discussed in greater detail. Recommendations are given. (au)

Guidelines for wireless technology in nuclear power plants

International Nuclear Information System (INIS)

Shankar, Ramesh

2003-01-01

As a result of technological breakthroughs, increased demand for the use of wireless technology is common in all industries today, and the electric power industry is no exception. Already, wireless technology has many applications in our industry, including - but not limited to - cellular phone systems, paging systems, two-way radio communication systems, dose management and tracking systems, and operator logs. EPRI has prepared a comprehensive guidelines document to support evaluation of wireless technologies in power plants for integrated (voice/data/video) communication, remote equipment and system monitoring, and to complement an electronic procedures support system (EPSS). The guidelines effort focuses on the development of a rules structure to support the deployment of wireless devices in a plant without compromising continuous, safe, and reliable operation. The guidelines document consists of two volumes. The first volume is introductory in nature and lays out the business case for applying wireless technologies. The intended audience is senior plant management personnel and utility industry executives. This volume contains background information, templates, worksheets, processes, and presentations that will allow internal sponsors to create business cases for piloting wireless projects. The second volume includes guidance on implementation and regulatory issues relevant to plant implementation. It covers the following application areas: implementation of integrated communication capability, equipment monitoring, work quality control, time and knowledge management, and business process automation. It details regulatory issues relevant to the adoption of wireless technology within nuclear power plants and offers guidance on preparing for and executing pilot and implementations of wireless technologies. The paper will cover important aspects on the guidelines. (author)

Advanced maintenance strategies for power plant operators--introducing inter-plant life cycle management

International Nuclear Information System (INIS)

Graeber, Ulrich

2004-01-01

One of the most important goals of competing power plant operators is to ensure safe operation of their plants, characterized by maximum availability throughout the entire life cycle and minimized specific generating costs. One parameter crucial to the total price of electricity--and one that can be actively influenced by the power plant operators--is maintenance. Up to 30% of all electricity generating costs accrue from maintenance. In the past years maintenance measures have been optimized particularly by the application and continuing development of testing and diagnostic techniques, by the increased level of system and component automation as well as more efficient organization structures. Despite the considerable success of these efforts, the potential for further cost reductions is still far from exhausted. But the risks connected to reliability, availability and safety need to be analyzed in greater detail in order to ensure the sustainability of the savings already achieved as well as those yet to be realized. The systematic application of condition-based maintenance and the implementation of structured life cycle management are essential requirements. An inter-plant approach is recommended to make a quick implementation of maintenance optimization potentials possible. Plant-specific improvement potentials can be established with the help of a best-practice comparison, and measures and priorities can be defined for realizing them. Creating an inter-plant database will allow experience and findings to be analyzed quickly and efficiently by experts and made available to all participants on a neutral platform. Despite--or maybe owing to--the increasingly competitive marketplace, a sustained reduction in the maintenance costs of power plant operators can only be achieved through a structured, inter-plant exchange of experience. The ZES offers the industry a suitable platform for cooperation with its 'Condition-Based Maintenance' research focus. The introduction

76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2011-01-10

... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437...

Automation of technical specification monitoring for nuclear power plants

International Nuclear Information System (INIS)

Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

1986-01-01

The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

Application of Nuclear Power Plant Simulator for High School Student Training

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

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

Application of Nuclear Power Plant Simulator for High School Student Training

International Nuclear Information System (INIS)

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

2014-01-01

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

Power-up of Fugen reactor and development of demonstration plant

International Nuclear Information System (INIS)

Sawai, Sadamu; Akebi, Michio; Yazaki, Akira.

1979-06-01

The Fugen Nuclear Power Station is the 165 MWe prototype plant characterized by heavy water-moderated, boiling light water-cooled, pressure tube type, and was developed by the Power Reactor and Nuclear Fuel Development Corporation, Japan. The plant went into commercial operation on March 20, 1979, in Tsuruga, Fukui Prefecture. Some delay in the overall schedule occurred due to the shortage of cement caused by the oil crisis, more stringent regulations as the result of stress corrosion cracking experienced in BWRs, and design modifications. All functional tests, the final check-up of the whole plant, and remaining modifying works had been completed by March 10, 1978. The minimum criticality was achieved with 22 mixed oxide fuel assemblies on March 20, 1978. Thereafter, the tests on reactor physics, plant dynamics, the performances of components and systems, and radiation and water chemistry have been carried out. 5 MWe was sent to grid system for the first time on July 29, 1978. The commercial operation of the plant was licenced by the Government on March 30, 1979. The conceptual design of the 600 MWe demonstration plant was finished in early 1979, and the detailed design is to be carried out in 1979 and 1980. The main design principle was incorporated in the conceptual design, but some modifications are to be made to reduce the power cost and to facilitate the easy maintenance. (Kako, I.)

Nuclear power plants in post-war thought

International Nuclear Information System (INIS)

Toya, Hiroshi

2015-01-01

This paper overviews how nuclear power plants have been talked about in the post-war thought. Science and technology sometimes significantly change the thinking way of humans, and nuclear power generation is an extreme technology. This paper overviews how nuclear power plants and humans are correlated. The following three points are discussed as the major issues of contemporary thought over nuclear power plants. First, on the danger of nuclear power plants, the risk of destructive power that nuclear energy has, and the danger of unreasoning development in science and technology civilization are discussed. Second, on the ethics issues surrounding nuclear power plants, the ethics that are based on unbalanced power relations, and democratic responsibility ethics based on discussion ethics are discussed. Third, on the issues of nuclear power plants and imagination, the limitations of democratic discussion surrounding nuclear power plants, the formation of imagination commensurate with the destructive power of nuclear power plants, and the formation of imagination that can represent the distant future are discussed. (A.O.)

Artificial intelligence expert system for nuclear power plant control and maintenance

International Nuclear Information System (INIS)

Westrom, G.B.

1987-01-01

A major concern in emergency response in a nuclear power plant is the lack of real experience with a catastrophic condition. Experts do more than just follow a set of rules. They have experience and insight into problems and are able to use their professional judgement. The objectives of this expert system are: Detect subtle off-normal trends in a reactor power plant system. Alert the operator with color graphics and synthesized voice commands. Identify the source of the problem and advise the operator on steps to restore the plant to normal operation. Provide an explanation facility and database to supply detailed information on component history and reasoning process. The RHRS (Residual Heat Removal System) was selected for the initial expert systems development because it is extremely important during refueling and cold shutdown operations

A novel design approach for small scale low enthalpy binary geothermal power plants

International Nuclear Information System (INIS)

Gabbrielli, Roberto

2012-01-01

Highlights: ► Off-design analysis of ORC geothermal power plants through the years and the days. ► Thermal degradation of the geothermal source reduces largely the plant performances. ► The plant capacity factor is low if the brine temperature is far from the design value. ► The performances through the life are more important than those at the design point. ► ORC geothermal power plants should be designed with the end-life brine temperature. - Abstract: In this paper a novel design approach for small scale low enthalpy binary geothermal power plants is proposed. After the suction, the hot water (brine) superheats an organic fluid (R134a) in a Rankine cycle and, then, is injected back underground. This fact causes the well-known thermal degradation of the geothermal resource during the years. Hence, the binary geothermal power plants have to operate with conditions that largely vary during their life and, consequently, the most part of their functioning is executed in off-design conditions. So, as the novel approach here proposed, the design temperature of the geothermal resource is selected between its highest and lowest values, that correspond to the beginning and the end of the operative life of the geothermal power plant, respectively. Hence, using a detailed off-design performance model, the optimal design point of the geothermal power plant is evaluated maximizing the total actualized cash flow from the incentives for renewable power generation. Under different renewable energy incentive scenarios, the power plant that is designed using the lowest temperature of the geothermal resource always results the best option.

Hybrid wind-power-distillation plant

Directory of Open Access Journals (Sweden)

Ninić Neven

2012-01-01

Full Text Available This paper reports and elaborates on the idea of a solar distiller and an offshore wind power plant operating together. The subject under discussion is a single-stage solar distillation plant with vaporization, using adiabatic expansion in the gravitational field inside a wind power plant supporting column. This scheme divides investment costs for electric power and distillate production. In the region of the Adriatic Sea, all electric power produced could be “converted” to hydrogen using less than 10% of the distillate produced.

Power plants 2009. Lectures

International Nuclear Information System (INIS)

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

Regional economic impacts of nuclear power plants

International Nuclear Information System (INIS)

Isard, W.; Reiner, T.; Van Zele, R.; Stratham, J.

1976-08-01

This study of economic and social impacts of nuclear power facilities compares a nuclear energy center (NEC) consisting of three surrogate sites in Ocean County, New Jersey with nuclear facilities dispersed in the Pennsylvania - New Jersey - Maryland area. The NEC studied in this report is assumed to contain 20 reactors of 1200 MW(e) each, for a total NEC capacity of 24,000 MW(e). Following the Introductory chapter, Chapter II discusses briefly the methodological basis for estimating impacts. This part of the analysis only considers impacts of wages and salaries and not purchase of construction materials within the region. Chapters III and IV, respectively, set forth the scenarios of an NEC at each of three sites in Ocean County, N.J. and of a pattern of dispersed nuclear power plants of total equivalent generating capacity. In each case, the economic impacts (employment and income) are calculated, emphasizing the regional effects. In Chapter V these impacts are compared and some more general conclusions are reported. A more detailed analysis of the consequences of the construction of a nuclear power plant is given in Chapter VI. An interindustry (input-output) study, which uses rather finely disaggregated data to estimate the impacts of a prototype plant that might be constructed either as a component of the dispersed scenario or as part of an NEC, is given. Some concluding remarks are given in Chapter VII, and policy questions are emphasized

Chemistry in power plants 2011

International Nuclear Information System (INIS)

2011-01-01

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

Nuclear power plants and the environment. Water samplings and releases

International Nuclear Information System (INIS)

Hartmann, Philippe; Bordet, Francois; Chevalier, Christian; Colin, Jean-Luc; Khalanski, Michel

2013-01-01

This voluminous and illustrated guide aims at giving detailed information on the nature of waters used by nuclear power plants and of releases, on how these samplings and controls are performed, on the associated risks for the environment and public health, and on how public is informed. After a general overview of these issues, a chapter addresses the protection of nature and biodiversity and the actions performed by EDF in this respect. The next chapter deals with public information. The next chapters discuss the water needs of a nuclear power plant, effluent releases and their impacts. Two chapters are dedicated to the monitoring and control of the environment, and to the various techniques of environmental metrology. Legal and regulatory aspects are then presented

Course in fire protection training for nuclear power plant personnel

International Nuclear Information System (INIS)

Walker, K.L.; Bates, E.F.; Randall, J.D.

1979-01-01

Proposed Regulatory Guide 1.120, entitled ''Fire Protection Guidelines for Nuclear Power Plants,'' provides detailed requirements for the overall fire protection programs at nuclear power plant sites in the United States. An essential element in such a program in the training of plant fire brigade personnel is the use of proper firefighting techniques and equipment. The Texas A and M University Nuclear Science Center (NSC) in conjunction with the Fire Protection Training Division of the Texas Engineering Extension Service has developed a one-week course to meet this training need. The program emphasizes hands-on exercises. The course is designed for up to 18 students with all protective clothing provided. Fire instructors are certified by the State of Texas, and registered nuclear engineers and certified health physicists supervise the radiological safety exercises. The first course was conducted during the week of January 8--12, 1979

Thermal power plant design and operation

CERN Document Server

Sarkar, Dipak

2015-01-01

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

Impacts of TMDLs on coal-fired power plants.

Energy Technology Data Exchange (ETDEWEB)

Veil, J. A.; Environmental Science Division

2010-04-30

from coal-fired power plants. If a state establishes a new or revised TMDL for one of these pollutants in a water body where a power plant is located, the next renewal of the power plant's National Pollution Discharge Elimination System (NPDES) permit is likely to include more restrictive limits. Power generators may need to modify existing operational and wastewater treatment technologies or employ new ones as TMDLs are revised or new ones are established. The extent to which coal-fired power plants may be impacted by revised and new TMDL development has not been well established. NETL asked Argonne to evaluate how current and potential future TMDLs might influence coal-fired power plant operations and discharges. This information can be used to inform future technology research funded by NETL. The scope of investigation was limited to several eastern U.S. river basins rather than providing a detailed national perspective.

Small-scale power plant potential in Finland

International Nuclear Information System (INIS)

Helynen, S.

1993-01-01

The presentation discusses the small-scale power plant potential in Finland. The study of the potential is limited to W-scale power plants producing both electric power and heat using solid fuels. The basic power plant dimensioning and electric power load determination is based on traditional boiler and gas turbine technology. The possible sites for power plants are communities using district heating, and industrialized sites needing process steam or heat. In 1990 70 % (17 TWh) of district heat was produced by gas turbines. Ten communities have an own back-pressure power plant, and 40 communities buy heat from industrial plants, owing back-pressure power generation. Additionally about 40 communes buy district heat from companies, owned by power companies and industry. Estimates of small-scale power plant potential has been made plant wise on the basis of district heat loads and industrial heat needs. The scale of the plants has been limited to scale 3 MWe or more. The choosing of the fuel depends on the local conditions. The cheapest indigenous fuels in many communes are industrial wood wastes, and both milled and sod peat. The potential of steam technology based small-scale power plants has been estimated to be about 50 plants in 1992/1993, the total power of which is 220-260 MW. The largest estimate is base situation, in which there would be energy cooperation between the communes and industry. The fuel used by the power plants would be about 5.4-6.6 TWh/a corresponding to 270-330 million FIM/a. The total investment costs of the plants would be about 2.0 billion FIM. The plants would employ about 250 persons, and the fuel supply (wood or peat) about 100 persons

Thermal Power Plant Performance Analysis

CERN Document Server

2012-01-01

The analysis of the reliability and availability of power plants is frequently based on simple indexes that do not take into account the criticality of some failures used for availability analysis. This criticality should be evaluated based on concepts of reliability which consider the effect of a component failure on the performance of the entire plant. System reliability analysis tools provide a root-cause analysis leading to the improvement of the plant maintenance plan.   Taking in view that the power plant performance can be evaluated not only based on  thermodynamic related indexes, such as heat-rate, Thermal Power Plant Performance Analysis focuses on the presentation of reliability-based tools used to define performance of complex systems and introduces the basic concepts of reliability, maintainability and risk analysis aiming at their application as tools for power plant performance improvement, including: ·         selection of critical equipment and components, ·         defini...

Progressive building methods in nuclear power plant construction

International Nuclear Information System (INIS)

Sikura, V.

1980-01-01

A detailed description is given of the new prospective technologies used in the construction of the Bohunice V-1 nuclear power plant. They include the use of steel and large-area forms, the use of profile sheets as a substitute for forms, assembled raw partitions, wall shells consisting of clamped porous concrete slabs, assembled roof shells, special finish of concrete walls, bearing wall deep foundation, the use of modern building machinery for concreting, reinforcing and welding works. (M.S.)

Construction and commissioning experience of evolutionary water cooled nuclear power plants

International Nuclear Information System (INIS)

2004-04-01

Electricity market liberalization is an established fact in several countries and there is a trend to adopt it in other countries. The essential aim of market liberalization is to improve the overall economic efficiency. In order that nuclear power remains a viable option for electricity generation, its costs should be competitive with alternative sources while, at the same time, it should have a safe and reliable operation record. The capital cost of nuclear power plants (NPPs) generally accounts for 43-70% of the total nuclear electricity generation costs, compared to 26-48% for coal plants and 13-32% for gas plants. Most of these expenditures are incurred during the construction phase of a NPP. The achievement of shorter construction periods using improved technology and construction methods has a significant benefit on the costs incurred prior to any production of electricity. This document is intended to make the recent worldwide experience on construction and commissioning of evolutionary water cooled NPPs available to Member States and especially to those with nuclear power plants under construction/planning, and to those seriously considering nuclear power projects in the future. The final aim is to assist utilities and other organizations in Member States to improve the construction of nuclear power plants and achieve shortened schedules and reduced costs without compromising quality and safety. This document aims to provide an overview of the most advanced technologies, methods and processes used in construction and commissioning of recent nuclear projects. To better achieve this objective the presentation is selectively focused more on the new developments rather than providing a full review of all issues related to construction and commissioning. The experience described in this TECDOC applies to managers, engineers, supervisors, technicians and workers in various organizations dealing with the site construction and commissioning of nuclear power plants

Power control of the Angra-2 Nuclear Power Plant

International Nuclear Information System (INIS)

Souza Mendes, J.E. de

1986-01-01

The systems for the power control of the Nuclear Power Plant Angra 2 have a high degree of automation so that few operator actions are required during power operation. The power control strategy and the operation principles of the control systems, here presented, make possible a great flexibility of the Plant operation. (Author) [pt

Organizing nuclear power plant operation

International Nuclear Information System (INIS)

Adams, H.W.; Rekittke, K.

1987-01-01

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

Risks of turbine generators at WWER-440 nuclear power plants

International Nuclear Information System (INIS)

Virolainen, T.; Marttila, J.; Aulamo, H.

1998-01-01

Many serious fires and incidents have occurred in the turbine halls of nuclear power plants, resulting in serious damage and long shutdown outages. Some of these incidents have endangered the safe shutdown of the plants because of the location of lack of vital fire protection safety systems. A detailed analysis is necessary for all those plants that have equipment important for safe shutdown located in the turbine hall or its vicinity without strict fire separation by fire rated barriers. A reduction in the fire frequencies of the turbine hall is an additional way of improving safety. This is possible by improving all aspects of turbine generator operation. (author)

Advanced power plant materials, design and technology

Energy Technology Data Exchange (ETDEWEB)

Roddy, D. (ed.) [Newcastle University (United Kingdom). Sir Joseph Swan Institute

2010-07-01

The book is a comprehensive reference on the state of the art of gas-fired and coal-fired power plants, their major components and performance improvement options. Selected chapters are: Integrated gasification combined cycle (IGCC) power plant design and technology by Y. Zhu, and H. C. Frey; Improving thermal cycle efficiency in advanced power plants: water and steam chemistry and materials performance by B. Dooley; Advanced carbon dioxide (CO{sub 2}) gas separation membrane development for power plants by A. Basile, F. Gallucci, and P. Morrone; Advanced flue gas cleaning systems for sulphur oxides (SOx), nitrogen oxides (NOx) and mercury emissions control in power plants by S. Miller and B.G. Miller; Advanced flue gas dedusting systems and filters for ash and particulate emissions control in power plants by B.G. Miller; Advanced sensors for combustion monitoring in power plants: towards smart high-density sensor networks by M. Yu and A.K. Gupta; Advanced monitoring and process control technology for coal-fired power plants by Y. Yan; Low-rank coal properties, upgrading and utilisation for improving the fuel flexibility of advanced power plants by T. Dlouhy; Development and integration of underground coal gasification (UCG) for improving the environmental impact of advanced power plants by M. Green; Development and application of carbon dioxide (CO{sub 2}) storage for improving the environmental impact of advanced power plants by B. McPherson; and Advanced technologies for syngas and hydrogen (H{sub 2}) production from fossil-fuel feedstocks in power plants by P. Chiesa.

Flow-accelerated corrosion in power plants. Revision 1

International Nuclear Information System (INIS)

Chexal, B.; Horowitz, J.; Dooley, B.

1998-07-01

Flow-Accelerated Corrosion (FAC) is a phenomenon that results in metal loss from piping, vessels, and equipment made of carbon steel. FAC occurs only under certain conditions of flow, chemistry, geometry, and material. Unfortunately, those conditions are common in much of the high-energy piping in nuclear and fossil-fueled power plants. Undetected, FAC will cause leaks and ruptures. Consequently, FAC has become a major issue, particularly for nuclear plants. Although major failures are rare, the consequences can be severe. In 1986, four men in the area of an FAC-induced pipe rupture were killed. Fossil plants too, are subject to FAC. In 1995, a failure at a fossil-fired plant caused two fatalities. In addition to concerns about personnel safety, FAC failures can pose challenges to plant safety. Regulatory agencies have therefore required nuclear utilities to institute formal programs to address FAC. Finally, a major FAC failure (like the one that happened in 1997 at a US nuclear power plant) can force a plant to shutdown and purchase replacement power at a price approaching a million dollars per day depending upon the MWe rating of the plant. A great deal of time and money has been spent to develop the technology to predict, detect, and mitigate FAC in order to prevent catastrophic failures. Over time, substantial progress has been made towards understanding and preventing FAC. The results of these efforts include dozens of papers, reports, calculations, and manuals, as well as computer programs and other tools. This book is written to provide a detailed treatment of the entire subject in a single document. Any complex issue requires balancing know-how, the risk of decision making, and a pragmatic engineering solution. This book addresses these by carrying out the necessary R and D and engineering along with plant knowledge to cover all quadrants of Chexal's four quadrant known-unknown diagram, as seen in Figure i

Seismic re-evaluation of the Tarapur atomic power plants 1 and 2

International Nuclear Information System (INIS)

Ingole, S.M.; Kumar, B.S.; Gupta, S.; Singh, U.P.; Giridhar, K.; Bhawsar, S.D.; Samota, A.; Chhatre, A.G.; Dixit, K.B.; Bhardwaj, S.A.

2004-01-01

Two Boiling Water Reactors (BWR) of 210 MWe each at Tarapur Atomic Power Station, Units-1 and 2 (TAPS-1-2) were commissioned in the year 1969. The safety related civil structures at TAPS had been designed for a seismic coefficient of 0.2 g and other structures for 0.1 g. The work of seismic re-evaluation of the TAPS-1-2 has been taken up in the year 2002. As two new Pressurized Heavy Water Reactor (PHWR) plants of 540 MWe each, Tarapur Atomic Power Project Units-3 and 4 (TAPP-3-4), are coming up in the vicinity of TAPS-1-2, detailed geological and seismological studies of the area around TAPS-1-2 are available. The same free-field ground motion as generated for TAPP-3-4 has been used for TAPS-1-2. The seismic re-evaluation of the plant has been performed as per the procedure given in IAEA, Safety Reports Series entitled 'Seismic Evaluation of Existing Nuclear Power Plants', and meeting the various codes and standards, viz., ASME, ASCE, IEEE standards etc. The Safety Systems (SS) and Safety Support Systems (SSS) are qualified by adopting detailed analysis and testing methods. The equipment in the SS and SSS have been qualified by conducting a walk-down as per the procedure given in Generic Implementation Procedure, Dept. of Energy (GIP--DOE), USA. The safety systems include the systems required for safe shutdown of the plant, one chain of decay heat removal and containment of activity. The safety support systems viz., Electrical, Instrumentation and Control and systems other than SS and SSS have been qualified by limited analysis, testing and mostly by following the procedure of walk-down. The paper brings out the details of the work accomplished during seismic re-evaluation of the two units of BWR at Tarapur. (authors)

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

1998-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Nighttime NOx Chemistry in Coal-Fired Power Plant Plumes

Science.gov (United States)

Fibiger, D. L.; McDuffie, E. E.; Dube, W. P.; Veres, P. R.; Lopez-Hilfiker, F.; Lee, B. H.; Green, J. R.; Fiddler, M. N.; Ebben, C. J.; Sparks, T.; Weinheimer, A. J.; Montzka, D.; Campos, T. L.; Cohen, R. C.; Bililign, S.; Holloway, J. S.; Thornton, J. A.; Brown, S. S.

2015-12-01

Nitrogen oxides (NOx = NO + NO2) play a key role in atmospheric chemistry. During the day, they catalyze ozone (O3) production, while at night they can react to form nitric acid (HNO3) and nitryl chloride (ClNO2) and remove O3 from the atmosphere. These processes are well studied in the summer, but winter measurements are more limited. Coal-fired power plants are a major source of NOx to the atmosphere, making up approximately 30% of emissions in the US (epa.gov). NOx emissions can vary seasonally, as well as plant-to-plant, with important impacts on the details of the plume chemistry. In particular, due to inefficient plume dispersion, nighttime NOx emissions from power plants are held in concentrated plumes, where rates of mixing with ambient O3 have a strong influence on plume evolution. We will show results from the aircraft-based WINTER campaign over the northeastern United States, where several nighttime intercepts of power plant plumes were made. Several of these intercepts show complete O3 titration, which can have a large influence on NOx lifetime, and thus O3 production, in the plume. When power plant NO emissions exceed background O3 levels, O3 is completely consumed converting NO to NO2. In the presence of O3, NO2 will be oxidized to NO3, which will then react with NO2 to form N2O5, which can then form HNO3 and/or ClNO2 and, ultimately, remove NOx from the atmosphere or provide next-day oxidant sources. If there is no O3 present, however, no further chemistry can occur and NO and NO2 will be transported until mixing with sufficient O3 for higher oxidation products. Modeling results of plume development and mixing, which can tell us more about this transport, will also be presented.

Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

International Nuclear Information System (INIS)

1997-07-01

This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs

Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs.

Cooling towers of nuclear power plants

International Nuclear Information System (INIS)

Mikyska, L.

1986-01-01

The specifications are given of cooling towers of foreign nuclear power plants and a comparison is made with specifications of cooling towers with natural draught in Czechoslovak nuclear power plants. Shortcomings are pointed out in the design of cooling towers of Czechoslovak nuclear power plants which have been derived from conventional power plant design. The main differences are in the adjustment of the towers for winter operation and in the designed spray intensity. The comparison of selected parameters is expressed graphically. (J.B.)

Advanced man-machine system for nuclear power plants

International Nuclear Information System (INIS)

Masui, Takao; Naito, Norio; Kato, Kanji.

1990-01-01

Recent development of artificial intelligence(AI) seems to offer new possibility to strengthen the performance of the operator support system. From this point of view, a national project of Advanced Man-Machine System Development for Nuclear Power Plant (MMS-NPP) has been carried out since 1984 as 8-year project. This project aims at establishing advanced operator support functions which support operators in their knowledge-based behaviors and smoother interface with the system. This paper describes the role of MMS-NPP, the support functions and the main feature of the MMS-NPP detailed design with its focus placed on the realization methods using AI technology of the support functions for BWR and PWR plants. (author)

Plant for the delivery of long-distance steam combined with a nuclear power plant

International Nuclear Information System (INIS)

Schueller, K.H.

1976-01-01

It is proposed that long-distance steam should not be directly discharged in order to avoid each posibility of spreading radioactively contaminated steam. As a heat transmitter, a surface heat exchanger should be chosen, the heating steam of the nuclear power station heating pressurized water whose pressure is higher then that of the heating steam. Long-distance steam generation then results from expanding the pressurized water. The plant is described in detail. (UWI) [de

Nuclear Power Plants. Revised.

Science.gov (United States)

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…

Regulatory approach of the monitoring the effectiveness of maintenance at nuclear power plants program

International Nuclear Information System (INIS)

Vajgel, Stefan

2009-03-01

The electrical power generation using nuclear power plants requires this installation being safety, reliable and available for the working periods. For this purpose, an adequate, effective and well conducted maintenance program makes an essential and useful tool to the owner of the plant. However, it is necessary to follow the regulatory requirements for this program implementation which monitories this maintenance effectiveness. There are Brazilian norms requirements which must be followed. The international regulatory guides establish these requirements in good details but it is necessary to verify if this methodology for implementing can be totally applied here in Brazil. Then, the american guide NUMARC 93-01 which details how can be implemented a program for this monitoring, shows some methods for using. In this thesis, the Delphi and Probabilistic Safety Analysis were briefly included because they were preferred for implementing this monitoring.in a Brazilian plant. The results which are being obtained show that, looking the regulatory aspects, the NUMARC 93-01 follows our regulations and gives good results for the plant management. (author)

Nuclear power plants and the environment

Energy Technology Data Exchange (ETDEWEB)

Barabas, K [Ceskoslovenska Komise pro Atomovou Energii, Prague

1978-05-01

The environmental impacts are compared of conventional coal-fired and oil-fired power plants and of nuclear power plants. The values are compared of SO/sub 2/, NO/sub 2/, ash and soot emissions with /sup 133/Xe and /sup 85/Kr fission products release and the requirement for air for diluting these emissions in the atmosphere is assessed. Also compared are thermal pollution from an oil-fired power plant and from PWR and fast reactor power plants. The conclusion is arrived at that nuclear energy can solve the problem of increasing demand for electric and heat power while reducing negative environmental impacts.

Nuclear power plants and the environment

International Nuclear Information System (INIS)

Barabas, K.

1978-01-01

The environmental impacts are compared of conventional coal-fired and oil-fired power plants and of nuclear power plants. The values are compared of SO 2 , NO 2 , ash and soot emmisions with 133 Xe and 85 Kr fission products release and the requirement for air for diluting these emissions in the atmosphere is assessed. Also compared are thermal pollution from an oil-fired power plant and from PWR and fast reactor power plants. The conclusion is arrived at that nuclear energy can solve the problem of increasing demand for electric and heat power while reducing negative environmental impacts. (O.K.)

HVDC transmission from nuclear power plant

International Nuclear Information System (INIS)

Yoshida, Yukio; Takenaka, Kiyoshi; Taniguchi, Haruto; Ueda, Kiyotaka

1980-01-01

HVDC transmission directly from a nuclear power plant is expected as one of the bulk power transmission systems from distant power generating area. Successively from the analysis of HVDC transmission from BWR-type nuclear power plant, this report discusses dynamic response characteristics of HVDC transmission (double poles, two circuits) from PWR type nuclear power plant due to dc-line faults (DC-1LG, 2LG) and ac-line faults (3LG) near inverter station. (author)

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

International Nuclear Information System (INIS)

2006-06-01

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

Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants

International Nuclear Information System (INIS)

2016-10-01

This publication supersedes IAEA-TECDOC-1511, Determining the Quality of Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants (published in 2006), which provided detailed information on technical features of a restricted scope PSA aimed at analysing only internal initiating events caused by random component failures and human errors, and accident sequences that may lead to reactor core damage during operation. The present publication extends the scope of the PSA to cover a broader range of internal and external hazards, and low power and shutdown modes of nuclear power plant operation. In addition, some PSA aspects relevant to lessons learned from the accident at the Fukushima Daiichi nuclear power plant are also considered

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

International Nuclear Information System (INIS)

Jiao Feng; Hou Qinmai; Che Shuwei

2013-01-01

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

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2005-01-01

This 2005 edition of the Elecnuc booklet summarizes in tables all numerical data relative to the nuclear power plants worldwide. These data come from the PRIS database managed by the IAEA. The following aspects are reviewed: 2004 highlights; main characteristics of reactor types; map of the French nuclear power plants on 2005/01/01; worldwide status of nuclear power plants at the end of 2004; units distributed by countries; nuclear power plants connected to the grid by reactor-type group; nuclear power plants under construction on 2004; evolution of nuclear power plant capacities connected to the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear power plants by country at the end 2004; performance indicator of PWR units in France; trend of the generation indicator worldwide; 2004 load factor by owners; units connected to the grid by countries at 12/31/2004; status of licence renewal applications in USA; nuclear power plants under construction at 12/31/2004; shutdown reactors; exported nuclear capacity in net MWe; exported and national nuclear capacity connected to the grid; exported nuclear power plants under construction or order; exported and national nuclear capacity under construction or order; recycling of plutonium in LWR; Mox licence plant projects; Appendix - historical development; acronyms, glossary

Chlorination for biofouling control in power plant cooling water system - a review

International Nuclear Information System (INIS)

Satpathy, K.K.; Ruth Nithila, S.D.

2008-01-01

Fresh water is becoming a rare commodity day by day and thus power plant authorities are turning into sea to make use of the copious amount of seawater available at an economical rate for condenser cooling. Unfortunately, biofouling; the growth and colonization of marine organisms affect the smooth operation of power plant cooling water systems. This is more so, if the plant is located in tropical climate having clean environment, which enhances the variety and density of organisms. Thus, biofouling needs to be controlled for efficient operation of the power plant. Biocide used for biofouling control is decided based on three major criteria viz: it should be economically, operationally and environmentally acceptable to the power plant authorities. Chlorine among others stands out on the top and meets all the above requirements in spite of a few shortcomings. Therefore it is no wonder that still chlorine rules the roost and chlorination remains the most common method of biofouling control in power plant cooling water system all over the world. Although, it is easier said than done, a good amount of R and D work is essential before a precise chlorination regime is put into pragmatic use. This paper discusses in details the chemistry of chlorination such as chlorine demand, chlorine decay, break point chlorination, speciation of chlorine residual and role of temperature and ammonia on chlorination in biofouling control. Moreover, targeted and pulse chlorination are also discussed briefly. (author)

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2000-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Automation technology in power plants

International Nuclear Information System (INIS)

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.)

Safety culture in the maintenance of nuclear power plants

International Nuclear Information System (INIS)

2005-01-01

Safety culture is the complexity of beliefs, shared values and behaviour reflected in making decisions and performing work in a nuclear power plant or nuclear facility. The definition of safety culture and the related concepts presented in the IAEA literature are widely known to experts. Since the publication of Safety Culture, issued by the IAEA as INSAG-4 in 1991, the IAEA has produced a number of publications on strengthening the safety culture in organizations that operate nuclear power plants and nuclear facilities. However, until now the focus has been primarily on the area of operations. Apart from operations, maintenance in plants and nuclear facilities is an aspect that deserves special attention, as maintenance activities can have both a direct and an indirect effect on equipment reliability. Adverse safety effects can arise, depending upon the level of skill of the personnel involved, safety awareness and the complexity of the work process. Any delayed effects resulting from challenges to maintenance can cause interruptions in operation, and hence affect the safety of a plant or facility. Building upon earlier IAEA publications on this topic, this Safety Report reviews how challenges to the maintenance of nuclear power plants can affect safety culture. It also highlights indications of a weakening safety culture. The challenges described are in areas such as maintenance management; human resources management; plant condition assessment and the business environment. The steps that some Member States have taken to address safety culture aspects are detailed and singled out as good practices, with a view to disseminating and exchanging experiences and lessons learned. Although this report is primarily directed at plant maintenance organizations, the subject matter is applicable to a wider audience, including plant contracting organizations and regulatory authorities

Advanced robot vision system for nuclear power plants

International Nuclear Information System (INIS)

Onoguchi, Kazunori; Kawamura, Atsuro; Nakayama, Ryoichi.

1991-01-01

We have developed a robot vision system for advanced robots used in nuclear power plants, under a contract with the Agency of Industrial Science and Technology of the Ministry of International Trade and Industry. This work is part of the large-scale 'advanced robot technology' project. The robot vision system consists of self-location measurement, obstacle detection, and object recognition subsystems, which are activated by a total control subsystem. This paper presents details of these subsystems and the experimental results obtained. (author)

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

International Nuclear Information System (INIS)

Jung Kun Lee; Byoung Sung Han

1997-01-01

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

Comparison between Different Power Sources for Emergency Power Supply at Nuclear Power Plants

International Nuclear Information System (INIS)

Lenasson, Magnus

2015-01-01

Currently the Swedish nuclear power plants are using diesel generator sets and to some extent gas turbines as their emergency AC power sources and batteries as their emergency DC power sources. In the laws governing Swedish nuclear activity, no specific power sources are prescribed. On the other hand, diversification of safety functions should be considered, as well as simplicity and reliability in the safety systems. So far the choices of emergency power sources have been similar between different power plants, and therefore this project investigated a number of alternative power sources and if they are suitable for use as emergency power on nuclear power plants. The goals of the project were to: - Define the parameters that are essential for rending a power source suitable for use at a nuclear power plant. - Present the characteristics of a number of power sources regarding the defined parameters. - Compile the suitability of the different power sources. - Make implementation suggestions for the less conventional of the investigated power sources. (unconventional in the investigated application) 10 different power sources in total have been investigated and to various degrees deemed suitable Out of the 10 power sources, diesel generators, batteries and to some extent gas turbines are seen as conventional technology at the nuclear power plants. In relation to them the other power sources have been assessed regarding diversification gains, foremost with regards to external events. The power sources with the largest diversification gains are: Internal steam turbine, Hydro power, Thermoelectric generators. The work should first and foremost put focus on the fact that under the right circumstances there are power sources that can complement conventional power sources and yield substantial diversification gains. This paper is a shortened version of the report 'Comparison between different power sources for emergency power supply at nuclear power plants'. The

Power control strategy of a photovoltaic power plant for microgrid applications

Energy Technology Data Exchange (ETDEWEB)

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

2008-07-01

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

Cooperation of nuclear, thermal and hydroelectric power plants in the power system

International Nuclear Information System (INIS)

1984-01-01

The conference heard 36 papers of which 23 were incorporated in INIS. The subjects discussed were: the development of power industry in Czechoslovakia, methods of statistical analysis of data regarding nuclear power plant operation, the incorporation of WWER nuclear power plants in the power supply system, the standardization of nuclear power plants, the service life of components, use of nuclear energy sources, performance of the reactor accident protection system, the use of nuclear power and heating plants in Hungary, risk analysis, optimization of nuclear power plants, accidents caused by leakage of the primary and secondary circuit. (J.P.)

Generation of floor response spectra for a model structure of nuclear power plant

International Nuclear Information System (INIS)

Vaidyanathan, C.V.; Kamatchi, P.; Ravichandran, R.; Lakshmanan, N.

2003-01-01

The importance of Nuclear power plants and the consequences of a nuclear accident require that the nuclear structures be designed for the most severe environmental conditions. Earthquakes constitutes major design consideration for the system, structures and equipment of a nuclear power plant. The design of structures on ground is based on the ground response spectra. Many important parts of a nuclear power plant facility are attached to the principal parts of the structure and respond in a manner determined by the structural response rather than by the general ground motion to which the structure is supported. Hence the seismic response of equipment is generally based on the response spectrum of the floor on which it is mounted. In this paper such floor response spectra have been generated at different nodes of a chosen model structure of a nuclear power plant. In the present study a detailed nonlinear time history analysis has been carried out on the mathematical model of the chosen Nuclear Power Plant model structure with the spectrum compatible time history. The acceleration response results of the time history analysis has been used in the spectral analysis and the response spectra are generated. Further peak broadening has been done to account for uncertainties in the material properties and soil characteristics. (author)

Intelligent Sun Tracking for a CPV Power Plant

International Nuclear Information System (INIS)

Maqsood, Ishtiaq; Emziane, Mahieddine

2010-01-01

The output of a solar panel is strongly dependent on the amount of perpendicular light flux falling on its surface, and a tracking system tries to parallel the vector area of the solar panel surface to the incident solar flux. We present a tracking technique based on a two-axis sun sensor which can be used to increase the power output from a number of CPV arrays connected together in a solar power plant. The outdoor testing procedure of the developed two-axis sun sensor is discussed. The detail of the algorithm used together with the related sun tracking equipment is also presented and discussed for the new two axes sun tracking system.

Nuclear material control systems for nuclear power plants

International Nuclear Information System (INIS)

1975-06-01

Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

Summary of nuclear power plant construction

International Nuclear Information System (INIS)

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.)

Nuclear power plant

International Nuclear Information System (INIS)

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

Application status and performance analysis of robot in nuclear power plants

International Nuclear Information System (INIS)

Liu Chengze; Yan Zhi; Deng Jingshan

2012-01-01

Application status of robot in nuclear power plants in some countries is summarized. The related robots include accident response robot, dismantling and cleaning robot, in-service inspection robot, special-purpose robot and so on. Finally, some key technologies such as the radiation-tolerance and reliability of the robot systems are analyzed in details. (authors)

75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2010-10-29

... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Notice of Withdrawal of...) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC, the licensee, to withdraw its... for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, located in Calvert County, MD. The...

VGB Congress 'Power Plants 2006'

International Nuclear Information System (INIS)

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.)

Nuclear power plant V-1

International Nuclear Information System (INIS)

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

Virtual power plant mid-term dispatch optimization

International Nuclear Information System (INIS)

Pandžić, Hrvoje; Kuzle, Igor; Capuder, Tomislav

2013-01-01

Highlights: ► Mid-term virtual power plant dispatching. ► Linear modeling. ► Mixed-integer linear programming applied to mid-term dispatch scheduling. ► Operation profit maximization combining bilateral contracts and the day-ahead market. -- Abstract: Wind power plants incur practically zero marginal costs during their operation. However, variable and uncertain nature of wind results in significant problems when trying to satisfy the contracted quantities of delivered electricity. For this reason, wind power plants and other non-dispatchable power sources are combined with dispatchable power sources forming a virtual power plant. This paper considers a weekly self-scheduling of a virtual power plant composed of intermittent renewable sources, storage system and a conventional power plant. On the one hand, the virtual power plant needs to fulfill its long-term bilateral contracts, while, on the other hand, it acts in the market trying to maximize its overall profit. The optimal dispatch problem is formulated as a mixed-integer linear programming model which maximizes the weekly virtual power plant profit subject to the long-term bilateral contracts and technical constraints. The self-scheduling procedure is based on stochastic programming. The uncertainty of the wind power and solar power generation is settled by using pumped hydro storage in order to provide flexible operation, as well as by having a conventional power plant as a backup. The efficiency of the proposed model is rendered through a realistic case study and analysis of the results is provided. Additionally, the impact of different storage capacities and turbine/pump capacities of pumped storage are analyzed.

The art and trend of nuclear power plants aging management and licenses renewal activity In USA

International Nuclear Information System (INIS)

Zhong Zhimin; Li Jinsong; Zhang Mengyi

2014-01-01

This paper briefly introduced the history and the art of nuclear power plants licenses renewal in United State. The aims, working scope, methodology, the art and trend of aging management and its role in license renewal process in United State nuclear power plants license renewal process were discussed in details. Furthermore, the aging management current research focus in United State was described. Then, take into account the AP serials Pressurized Water Reactor and nuclear safety requirements in the regulatory and safety guide in China, some suggestions and recommendation on nuclear power plants aging management were introduced, which will be helpful when we developed related aging management works in China. (authors)

The Sydvaerme project: District heating from the Barsebeck nuclear power plant

International Nuclear Information System (INIS)

Josefsson, L.

1977-01-01

The paper presents a summary report of a study on district heating from Barsebeck Nuclear Power Plant in Sweden, prepared cooperatively by the cities of Malmoe, Lund, Helsingborg, Landskrona and the electric power company Sydkraft. A future number 3 generating set at the Barsebeck nuclear power station could be designed for combined production of heat and electric power. The generating set could be completed after 1983, and could then supply about 65% of total district heating requirements. The first stage of the investigation includes a proposal for a technically feasible solution, sufficiently detailed to permit both technical and economic evaluation of the project. (author)

Nuclear power plants maintenance

International Nuclear Information System (INIS)

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

Nuclear power plant outages

International Nuclear Information System (INIS)

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

Physical and financial virtual power plants

International Nuclear Information System (INIS)

Willems, Bert

2005-01-01

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

Considerations for Applying Design Extension Conditions to Domestic Nuclear Power Plants

International Nuclear Information System (INIS)

Ryu, Yongho

2013-01-01

The concept is designed to include more serious accidents than the existing design basis accidents considering additional failures. Design extension conditions can be derived based on engineering judgments, deterministic analysis or probabilistic analysis of the nuclear power plants. They are used to secure practical response capabilities to prevent or mitigate accidents. They may also require the deployment of additional safety equipment for existing nuclear power plants currently in operation. Though the general requirements of design extension conditions are described under the IAEA standards, no specific guidelines have been presented as required for their actual application to the nuclear power plant design. Furthermore, there is great variation between countries in implementing the requirements of design extension conditions. Therefore, for the actual application, considerable effort should be made among relevant organizations to establish detailed requirements of the design extension conditions. Such activities could constitute a part of the efforts of the nuclear community to meet the general public's expectations concerning the safety of nuclear power plants. The introduction of design extension conditions is expected to be a means of systematically enhancing the safety of nuclear power plants. Yet, there exists great differences in terms of the scope of analysis and the acceptance criteria, as no uniform practices have yet been established in applying the specific requirements for design extension conditions. A careful review is required in terms of the technical basis for setting the requirements, including those pertaining to the scope of analysis and the acceptance criteria. The introduction of these new requirements to Korean nuclear power plants may cause unexpected problems. Therefore, it is desirable for the regulatory agency to systematically assess the impact of design extension conditions and to discuss the arising issues with the stake holder

Nonlinear Dynamic Model of Power Plants with Single-Phase Coolant Reactors

International Nuclear Information System (INIS)

Vollmer, H.

1968-12-01

The traditional way of developing dynamic models for a specific nuclear power plant and for specific purpose seems rather uneconomical, as much of the information often can not be utilized if the plant design or the required accuracy of the calculation is desired to be changed. It is therefore suggested that the model development may be made more systematic, general and flexible by - applying the 'box of bricks' system, where the main components of a nuclear power plant are treated separately and combined afterwards according to a given flow scheme, - a dynamic determination of the components which is as general as possible without taking into account those details which have a minor influence on the overall dynamics, - providing approximations of the more rigorous solution sufficient to meet the user s requirements on accuracy, - proper use of computers. A dynamic model for single-phase coolant reactor plants is established along these lines. By separation of the nonlinear and linear parts of the system, application of Laplace transformation and proper approximations, and the use of a hybrid computer it seems possible to determine the (nonlinear) dynamic behaviour of such a plant for perturbations which are not so large that phase changes of physical parameters occur, e. g. fuel does not melt. The model is applied to a steam cooled fast reactor power plant

Nonlinear Dynamic Model of Power Plants with Single-Phase Coolant Reactors

Energy Technology Data Exchange (ETDEWEB)

Vollmer, H

1968-12-15

The traditional way of developing dynamic models for a specific nuclear power plant and for specific purpose seems rather uneconomical, as much of the information often can not be utilized if the plant design or the required accuracy of the calculation is desired to be changed. It is therefore suggested that the model development may be made more systematic, general and flexible by - applying the 'box of bricks' system, where the main components of a nuclear power plant are treated separately and combined afterwards according to a given flow scheme, - a dynamic determination of the components which is as general as possible without taking into account those details which have a minor influence on the overall dynamics, - providing approximations of the more rigorous solution sufficient to meet the user s requirements on accuracy, - proper use of computers. A dynamic model for single-phase coolant reactor plants is established along these lines. By separation of the nonlinear and linear parts of the system, application of Laplace transformation and proper approximations, and the use of a hybrid computer it seems possible to determine the (nonlinear) dynamic behaviour of such a plant for perturbations which are not so large that phase changes of physical parameters occur, e. g. fuel does not melt. The model is applied to a steam cooled fast reactor power plant.

The database system of the real-time dose appreciation for Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Jiang Li; Chai Luquan

1993-01-01

The paper is about the data base system of the real-time dose appreciation for Qinshan Nuclear Power Plant and describes in detail the design of the system, the data structure, the programming and the characteristics

Standard model for safety analysis report of hexafluoride power plants from natural uranium

International Nuclear Information System (INIS)

1983-01-01

The standard model for safety analysis report for hexafluoride production power plants from natural uranium is presented, showing the presentation form, the nature and the degree of detail, of the minimal information required by the Brazilian Nuclear Energy Commission - CNEN. (E.G.) [pt

Actual status and future outlook of Fukushima prefecture for accepting power plants

International Nuclear Information System (INIS)

Origasa, Yoshiro

1976-01-01

The fundamental attitude of Fukushima prefecture to wrestle with nuclear power generation is explained after having described the details of inviting nuclear power plants. The prefecture intends to promote the nuclear power development in cooperation with the government, related cities, towns and villages, and electric power companies, and to develop the Futaba area, the coastal region of Pacific Ocean belonging to the low-developed area, by turning it to the base of nuclear power generation. The prefecture has improved its organization to strengthen to nuclear power administration. The prefecture also has concluded the convention on the security for nuclear power plants with Tokyo Electric Power Co. It takes care of the propagation of knowledge concerning nuclear energy and is endeavoring to provide the accurate and impartial information. The problem in promoting nuclear power generation is nothing but to obtain the consensus of inhabitants for the location of nuclear power plants. Problems on warm water discharge, employment, and of enterprises in the area inroad are to be considered on the basis of the coexistence and coprosperity of local community and power stations. The prefecture needs more powerful public relations on nuclear power, security, and fulfillment of the policy for environmental preservation, and enforcement of environmental assessment, by the government. It also demands that the enterprises complete the system that they can have their own function of the environment control. The abundant related reference are added at the end. (Wakatsuki, Y.)

Site selection for nuclear power plants and geologic seismologia influence

International Nuclear Information System (INIS)

Castro Feitosa, G. de.

1985-01-01

The site selection for nuclear power plants is analised concerning to the process, methodology and the phases in an overall project efforts. The factors affecting are analised on a general viewpoint, showing the considerations given to every one. The geologic and seismologic factors influence on the foundation design are more detailed analised, with required investigation and procedures accordingly sub-soil conditions in the site [pt

Hydraulic Power Plant Machine Dynamic Diagnosis

Directory of Open Access Journals (Sweden)

Hans Günther Poll

2006-01-01

Full Text Available A method how to perform an entire structural and hydraulic diagnosis of prototype Francis power machines is presented and discussed in this report. Machine diagnosis of Francis units consists on a proper evaluation of acquired mechanical, thermal and hydraulic data obtained in different operating conditions of several rotary and non rotary machine components. Many different physical quantities of a Francis machine such as pressure, strains, vibration related data, water flow, air flow, position of regulating devices and displacements are measured in a synchronized way so that a relation of cause an effect can be developed for each operating condition and help one to understand all phenomena that are involved with such kind of machine. This amount of data needs to be adequately post processed in order to allow correct interpretation of the machine dynamics and finally these data must be compared with the expected calculated data not only to fine tuning the calculation methods but also to accomplish fully understanding of the influence of the water passages on such machines. The way how the power plant owner has to operate its Francis machines, many times also determined by a central dispatcher, has a high influence on the fatigue life time of the machine components. The diagnostic method presented in this report helps one to understand the importance of adequate operation to allow a low maintenance cost for the entire power plant. The method how to acquire these quantities is discussed in details together with the importance of correct sensor balancing, calibration and adequate correlation with the physical quantities. Typical results of the dynamic machine behavior, with adequate interpretation, obtained in recent measurement campaigns of some important hydraulic turbines were presented. The paper highlights the investigation focus of the hydraulic machine behavior and how to tailor the measurement strategy to accomplish all goals. Finally some

Training of power plant operating personnel

International Nuclear Information System (INIS)

Kraftwerksschule, E.V.

1986-01-01

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

Wear oxidation of evaporator coils in fluidised bed captive power plants

International Nuclear Information System (INIS)

Ghosal, S.K.; De, P.K.

2000-01-01

Combustion of pulverised coal or gas to form steam in thermal power plants is a common practice. Corrosion of water-wall, superheater and reheater tubes is the typical problem faced in these power plants. Modification of process conditions, redesigning of equipment and selection of more corrosion resistant materials are few methods which have been tried to combat corrosion to a certain extent. Restricted heat transfer efficiency is another problem associated with these power plants. In order to bring upon improvements, fluidized bed combustors are being used in some advanced thermal power plants at present because of excellent combustion and heat transfer efficiencies. Even with low grade coals, higher combustion efficiency could be achieved in these combustors due to excellent gas/solid chemical reactivity at relatively low reaction temperatures. Further improvements in in-bed heat transfer and bed temperature uniformity have been possible with the use of sand in bed. However, erosion, corrosion and combined erosion/corrosion are some of the major modes of material degradation associated with these fluidized bed combustors using sand. Recently in a captive power unit using bubbling fluidized bed combustors containing sand, evaporator coils made of carbon steel were seen to be severely affected by erosion corrosion. The directional nature of metal removal from the studs, tube OD and ultimately the rupture of the thinned tube wall confirmed the above observation. Microstructural examinations showed loss of carbon at certain places including those near the leaked/punctured regions at the prevailing bed temperature of 850 deg C. This paper describes the detailed investigations carried out on wear oxidation phenomenon occurred in a captive thermal power plant using advanced bubbling fluidized bed combustors. (author)

Human factors in nuclear power plants

International Nuclear Information System (INIS)

Pack, R.W.

1978-01-01

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

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

Economic consequences of alternative nuclear power plant lifetimes in Germany

International Nuclear Information System (INIS)

Lindenberger, D.; Wissen, R.; Bartels, M.; Buttermann, H.G.; Hillebrand, B.

2006-01-01

The coalition agreement of the Christian Democratic (CDU), Christian Social (CSU), and Social Democratic (SPD) parties contains a provision under which the existing regulations about phasing out the peaceful use of nuclear power will remain in force because of different opinions about the use of nuclear power in Germany. This article studies the consequences of longer lifetimes of the nuclear power plants currently in operation as compared to the provisions in opt-out legislation. The details examined include the effects of longer nuclear power plant lifetimes on the development of generating capacities in Germany, electricity generation, fuel consumption and fuel imports, the resultant CO 2 emissions, costs of electricity generation and electricity prices as well as the associated impact on production and employment in this sector and in industry as a whole. A summary is presented of the findings of a comprehensive study published under the same title in October 2005. The study was compiled by the Institute of Power Economics of the University of Cologne (EWI) and by Energy Environment Forecast Analysis GmbH, and had been commissioned by the Federation of German Industries (BDI). (orig.)

Cardinal principle and application practice of 3D digital model design for nuclear power plant

International Nuclear Information System (INIS)

Wang Ruobing; Wu Yan

2005-01-01

The practical application of 3D digital model design at nuclear power plants was introduced in detail in the paper. The whole process for system choice, program constitution, model design and project practice were also summarized. By demonstrating the cardinal principal and application practice of 3D digital model design as an important sub-project of CGNPC Digital Plant, the paper validates the rationality and validity of the major architecture system and program configuration of the digital plant, carries out beneficial attempt and study in the overall power plant life engineering management and site practice, and has achieved significant engineering and social benefits. The success of practices in the project accelerates the extended and extensive application of Digital Plant in the operation and maintenance simulation of Daya Bay and Ling'ao Nuclear Power Plants, and the engineering design management for Ling'ao II and III of CGNPC on a consolidated basis. (authors)

Development of instructors for nuclear power plant personnel training

International Nuclear Information System (INIS)

2004-06-01

In 1996 the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook, which provides guidance with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the development of instructors for NPP personnel training. The quality of nuclear power plant personnel training is strongly dependent on the availability of competent instructors. Instructors must have a comprehensive practical as well as theoretical understanding of all aspects of the subjects being taught and the relationship of the subject to nuclear plant operation. Instructors should have the appropriate knowledge, skills and attitudes (KSAs) in their assigned areas of responsibility. They should thoroughly understand all aspects of the contents of the training programmes and the relationship between these contents and overall plant operation. This means that they should be technically competent and show credibility with the trainees and other plant personnel. In addition, the instructors should be familiar with the basics of adult learning and a systematic approach to training, and should have adequate instructional and assessment skills. This TECDOC provides practical guidance on various aspects of instructor selection, development and deployment, by quoting actual examples from different countries. It highlights the importance of having an appropriate training policy, especially considering the various organisational arrangements that exist in different utilities/countries. This should result in: plant performance improvement, improved human performance, meeting goals and objectives of the business (quality, safety, productivity), and improving training programs. This publication is available in two formats - as a conventional printed

Effect of nuclear power on CO₂ emission from power plant sector in Iran.

Science.gov (United States)

Kargari, Nargess; Mastouri, Reza

2011-01-01

It is predicted that demand for electricity in Islamic Republic of Iran will continue to increase dramatically in the future due to the rapid pace of economic development leading to construction of new power plants. At the present time, most of electricity is generated by burning fossil fuels which result in emission of great deal of pollutants and greenhouse gases (GHG) such as SO₂, NOx, and CO₂. The power industry is the largest contributor to these emissions. Due to minimal emission of GHG by renewable and nuclear power plants, they are most suitable replacements for the fossil-fueled power plants. However, the nuclear power plants are more suitable than renewable power plants in providing baseload electricity. The Bushehr Nuclear Power Plant, the only nuclear power plant of Iran, is expected to start operation in 2010. This paper attempts to interpret the role of Bushehr nuclear power plant (BNPP) in CO₂ emission trend of power plant sector in Iran. In order to calculate CO₂ emissions from power plants, National CO₂ coefficients have been used. The National CO₂ emission coefficients are according to different fuels (natural gas, fuels gas, fuel oil). By operating Bushehr Nuclear Power Plant in 2010, nominal capacity of electricity generation in Iran will increase by about 1,000 MW, which increases the electricity generation by almost 7,000 MWh/year (it is calculated according to availability factor and nominal capacity of BNPP). Bushehr Nuclear Power Plant will decrease the CO₂ emission in Iran power sector, by about 3% in 2010.

TAPCHAN Wave Power Plants

Energy Technology Data Exchange (ETDEWEB)

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.

Plant life management and maintenance technologies for nuclear power plants

International Nuclear Information System (INIS)

Ikegami, Tsukasa; Aoki, Masataka; Shimura, Takao; Kaimori, Kimihiro; Koike, Masahiro

2001-01-01

Nuclear power generation occupying an important position for energy source in Japan and supplying about one third of total electric power usage is now required for further upgrading of its economics under regulation relaxation of electric power business. And, under execution retardation of its new planning plant, it becomes important to operate the already established plants for longer term and to secure their stability. Therefore, technical development in response to the plant life elongation is promoted under cooperation of the Ministry of Economics and Industries, electric power companies, literate, and plant manufacturers. Under such conditions, the Hitachi, Ltd. has progressed some technical developments on check inspection, repairs and maintenance for succession of the already established nuclear power plants for longer term under securing of their safety and reliability. And in future, by proposing the check inspection and maintenance program combined with these technologies, it is planned to exert promotion of maintenance program with minimum total cost from a viewpoint of its plant life. Here were described on technologies exerted in the Hitachi, Ltd. such as construction of plant maintenance program in response to plant life elongation agreeing with actual condition of each plant, yearly change mechanism grasping, life evaluation on instruments and materials necessary for maintenance, adequate check inspection, repairs and exchange, and so forth. (G.K.)

PA activity by using nuclear power plant safety demonstration and analysis

International Nuclear Information System (INIS)

Tsuchiya, Mitsuo; Kamimae, Rie

1999-01-01

INS/NUPEC presents one of Public acceptance (PA) methods for nuclear power in Japan, 'PA activity by using Nuclear Power Plant Safety Demonstration and Analysis', by using one of videos which is explained and analyzed accident events (Loss of Coolant Accident). Safety regulations of The National Government are strictly implemented in licensing at each of basic design and detailed design. To support safety regulation activities conducted by the National Government, INS/NLTPEC continuously implement Safety demonstration and analysis. With safety demonstration and analysis, made by assuming some abnormal conditions, what impacts could be produced by the assumed conditions are forecast based on specific design data on a given nuclear power plants. When analysis results compared with relevant decision criteria, the safety of nuclear power plants is confirmed. The decision criteria are designed to help judge if or not safety design of nuclear power plants is properly made. The decision criteria are set in the safety examination guidelines by taking sufficient safety allowance based on the latest technical knowledge obtained from a wide range of tests and safety studies. Safety demonstration and analysis is made by taking the procedure which are summarized in this presentation. In Japan, various PA (Public Acceptance) pamphlets and videos on nuclear energy have been published. But many of them focused on such topics as necessity or importance of nuclear energy, basic principles of nuclear power generation, etc., and a few described safety evaluation particularly of abnormal and accident events in accordance with the regulatory requirements. In this background, INS/NUPEC has been making efforts to prepare PA pamphlets and videos to explain the safety of nuclear power plants, to be simple and concrete enough, using various analytical computations for abnormal and accident events. In results, PA activity of INS/NUPEC is evaluated highly by the people

Design and Tuning of Wind Power Plant Voltage Controller with Embedded Application of Wind Turbines and STATCOMs

DEFF Research Database (Denmark)

Petersen, Lennart; Kryezi, Fitim; Iov, Florin

2017-01-01

This study addresses a detailed design and tuning of a wind power plant voltage control with reactive power contribution of wind turbines and static synchronous compensators (STATCOMs). First, small-signal models of a single wind turbine and STATCOM are derived by using the state-space approach....... A complete phasor model of the entire wind power plant is constructed, being appropriate for voltage control assessment. An exemplary wind power plant located in the United Kingdom and the corresponding grid code requirements are used as a base case. The final design and tuning process of the voltage...... controller results in a guidance, proposed for this particular control architecture. It provides qualitative outcomes regarding the parametrisation of each individual control loop and how to adjust the voltage controller depending on different grid stiffnesses of the wind power plant connection...

Assessing the potential role of concentrated solar power (CSP) for the northeast power system of Brazil using a detailed power system model

International Nuclear Information System (INIS)

Fichter, Tobias; Soria, Rafael; Szklo, Alexandre; Schaeffer, Roberto; Lucena, Andre F.P.

2017-01-01

One of the technologies that stand out as an alternative to provide additional flexibility to power systems with large penetration of variable renewable energy (VRE), especially for regions with high direct normal irradiation (DNI), is concentrated solar power (CSP) plants coupled to thermal energy storage (TES) and back-up (BUS) systems. Brazil can develop this technology domestically, especially in its Northeast region, where most of VRE capacity is being deployed and where lies most of the CSP potential of the country. This work applies the Capacity Expansion Model REMix-CEM, which allows considering dispatch constraints of thermal power plants in long-term capacity expansion optimization. REMix-CEM calculates the optimal CSP plant configuration and its dispatch strategy from a central planning perspective. Results showed that the hybridization of CSP plants with jurema-preta biomass (CSP-BIO) becomes a least-cost option for Brazil by 2040. CSP-BIO contributes to the Northeast power system by regularizing the energy imbalance that results from the large-scale VRE expansion along with conventional inflexible power plants. CSP-BIO plants are able to increase frequency response and operational reserve services and can provide the required additional flexibility that the Northeast power system of Brazil will require into the future. - Highlights: • Concentrating solar power (CSP) plants provide flexibility to power systems. • CSP configuration is optimized endogenously during capacity expansion optimization. • CSP hybridized with biomass supports grid-integration of variable renewable energy. • CSP become the least-cost option for the Northeast power system of Brazil by 2040.

Turbines, generators and associated plant incorporating modern power system practice

CERN Document Server

Littler, DJ

1992-01-01

The introduction of new 500 MW and 660 MW turbine generator plant in nuclear, coal- and oil-fired power stations has been partly responsible for the increase in generating capacity of the CEGB over the last 30 years. This volume provides a detailed account of experience gained in the development, design, manufacture, operation and testing of large turbine-generators in the last 20 years. With the advance in analytical and computational techniques, the application of this experience to future design and operation of large turbine-generator plant will be of great value to engineers in the indust

Ageing management of nuclear power plant - the Tarapur experience

International Nuclear Information System (INIS)

Anilkumar, K.R.; Das, P.K.; Bhattacharjee, S.; Ramamurty, U.

2006-01-01

Tarapur Atomic Power Station, the longest serving Nuclear Power Plant in the Asian continent has completed 36 years of successful operation and generated more than 70,000 million units of electric power. Built in late sixties, with the state-of-the-art safety features prevailing then, TAPS through the process of evolution has become safer plant due to efforts of upgradation, renovation and refurbishment prompted by the station's operating experience, feed back from overseas reactors, lessons learnt from nuclear incidents, accidents and fresh review of design basis and safety analysis of the plant. All components of a Nuclear power plant experience some degradation with time. The Reactor Pressure Vessels (RPV) designed for 40 effective full power years (EFPY) of operation have operated for less than 20 EFPY and the material condition is assessed to be fit for some more years of service. The condition of the containment and main plant buildings was assessed to be satisfactory. The Ageing Management Programme (AMP) involved identification of key systems, structures and components (SSCs) that may experience degradation due to ageing, and take corrective measures through maintenance, repair and/or replacement. The identified components were classified as major critical components, important systems and other critical components. For each component mode of degradation was identified, ageing assessment was done and action plan was finalized. Replacement of some important equipment like 3 x 50 % capacity Emergency Diesel Generators (EDG) with 3 x 100 % capacity EDG, Salt Service Water (SSW) pumps, Control rod drive (CRD) pumps, Emergency Condenser tube bundles, Station battery has been done on the basis of condition monitoring and to obviate common cause failure and enhance the system reliability. Samples of Safety related cables were subjected to residual life assessment (RLA) and replacement action firmed up on the basis of the RLA findings. Condition survey of Main

Wind power plant

Energy Technology Data Exchange (ETDEWEB)

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.

Managing the first nuclear power plant project

International Nuclear Information System (INIS)

2007-05-01

would be of benefit to the countries, utilities and other organizations involved in such endeavors. The IAEA has collated worldwide experience and developed guidance in all aspects of managing nuclear power plant projects. This guidance was published in a number of technical documents issued during the last two decades. The present publication is aimed to select some relevant elements that provide a general overview of the main activities in managing the first nuclear power project and lists those specific publications where the reader can obtain further detailed information. Target audience is the decision makers, advisers and senior managers in the governmental organizations, utilities, industrial organizations and regulatory bodies in the countries desiring to launch the first nuclear power project This publication was produced within IAEA program directed to increase the capability of Member States to plan and implement nuclear power programs and to establish and enhance national nuclear infrastructure

Reliability of emergency ac power systems at nuclear power plants

International Nuclear Information System (INIS)

Battle, R.E.; Campbell, D.J.

1983-07-01

Reliability of emergency onsite ac power systems at nuclear power plants has been questioned within the Nuclear Regulatory Commission (NRC) because of the number of diesel generator failures reported by nuclear plant licensees and the reactor core damage that could result from diesel failure during an emergency. This report contains the results of a reliability analysis of the onsite ac power system, and it uses the results of a separate analysis of offsite power systems to calculate the expected frequency of station blackout. Included is a design and operating experience review. Eighteen plants representative of typical onsite ac power systems and ten generic designs were selected to be modeled by fault trees. Operating experience data were collected from the NRC files and from nuclear plant licensee responses to a questionnaire sent out for this project

Nuclear power plant operator licensing

International Nuclear Information System (INIS)

1997-01-01

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

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2003-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2002 was made up on bases of answers on questionnaires from 65 electric power companies and other nuclear organizations in 28 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

Risks in the operation of hydroelectric power plants and nuclear power in Brazil

International Nuclear Information System (INIS)

Goldemberg, J.

1986-01-01

A comparison between the utilization of electrical energy generated by hydroelectric power plant and nuclear power plant is made. The risks from nuclear installations and the environmental effects of hydroelectric power plants and nuclear power plants are presented. (E.G.) [pt

Nuclear power plant operating experience, 1976

International Nuclear Information System (INIS)

1977-11-01

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

The operation of nuclear power plants

International Nuclear Information System (INIS)

Brosche, D.

1992-01-01

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

Guidelines for the application and use of valves in power plant systems

International Nuclear Information System (INIS)

Brooks, B.

1991-01-01

The improper application, incorrect use, and ineffective maintenance of valves in power plant systems have been determined to be the cause of significant losses in plant availability. Such practices may additionally impact the safe operation of the plant. Numerous programs have been initiated, particularly in the nuclear power generation industry, to address these problems and excellent strides have been taken in that direction. Plant operating data, however, continues to indicate major losses in plant availability attributable to these sources. Although there exists significant knowledge and expertise in valve technology in the valve industry and in the power generation industry, the application of these factors, in preventing and resolving problems, has not been effectively utilized. Detailed information is difficult to glean from numerous sources and may often be restricted by proprietary considerations. Lessons learned in resolving problems have not been broadly disseminated in the industry with the result that individual utilities may be addressing problems unaware that a neighbor utility has already effectively resolved this same problem. To aid the power generation industry in improving upon this condition, EPRI initiated a project to develop 'Guide for the Application and Use of Valves in Power Plant Systems' (RP2233-5). A draft of the document was reviewed by an industry group whose major comment was the need to achieve a more readable text in which information on specific areas of concern is readily accessible. This rewriting has been accomplished along the lines of valve functional requirements. This paper presents an introduction, a summary, and a road map on how to use the guidebook

Power plant asset market evaluations: Forecasting the costs of power production

Energy Technology Data Exchange (ETDEWEB)

Lefton, S A; Grunsrud, G P [Aptech Engineering Services, Inc., Sunnyvale, CA (United States)

1999-12-31

This presentation discusses the process of evaluating and valuing power plants for sale. It describes a method to forecast the future costs at a power plant using a portion of the past fixed costs, variable energy costs, and most importantly the variable cycling-related wear-and-tear costs. The presentation then discusses how to best determine market share, expected revenues, and then to forecast plant future costs based on future expected unit cycling operations. The presentation concludes with a section on recommendations to power plant buyers or sellers on how to manage the power plant asset and how to increase its market value. (orig.) 4 refs.

Power plant asset market evaluations: Forecasting the costs of power production

Energy Technology Data Exchange (ETDEWEB)

Lefton, S.A.; Grunsrud, G.P. [Aptech Engineering Services, Inc., Sunnyvale, CA (United States)

1998-12-31

This presentation discusses the process of evaluating and valuing power plants for sale. It describes a method to forecast the future costs at a power plant using a portion of the past fixed costs, variable energy costs, and most importantly the variable cycling-related wear-and-tear costs. The presentation then discusses how to best determine market share, expected revenues, and then to forecast plant future costs based on future expected unit cycling operations. The presentation concludes with a section on recommendations to power plant buyers or sellers on how to manage the power plant asset and how to increase its market value. (orig.) 4 refs.

Power plant asset market evaluations: Forecasting the costs of power production

International Nuclear Information System (INIS)

Lefton, S.A.; Grunsrud, G.P.

1998-01-01

This presentation discusses the process of evaluating and valuing power plants for sale. It describes a method to forecast the future costs at a power plant using a portion of the past fixed costs, variable energy costs, and most importantly the variable cycling-related wear-and-tear costs. The presentation then discusses how to best determine market share, expected revenues, and then to forecast plant future costs based on future expected unit cycling operations. The presentation concludes with a section on recommendations to power plant buyers or sellers on how to manage the power plant asset and how to increase its market value. (orig.) 4 refs

Damping of Low Frequency Power System Oscillations with Wind Power Plants

DEFF Research Database (Denmark)

Adamczyk, Andrzej Grzegorz

of wind power plants on power system low frequency oscillations and identify methods and limitations for potential contribution to the damping of such oscillations. Consequently, the first part of the studies focuses on how the increased penetration of wind power into power systems affects their natural...... oscillatory performance. To do so, at first a generic test grid displaying a complex inter-area oscillation pattern is introduced. After the evaluation of the test grid oscillatory profile for various wind power penetration scenarios, it is concluded that full-converter based wind power plant dynamics do......-synchronous power source. The main body of the work is devoted to the damping control design for wind power plants with focus on the impact of such control on the plant operation. It can be expected that the referred impact is directly proportional to the control effort, which for power processing devices should...

Thermodynamic optimization of power plants

NARCIS (Netherlands)

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

Development of chemistry management for Onagawa Nuclear Power Plant

International Nuclear Information System (INIS)

Honda, Kazuaki; Sato, Junichi; Maeda, Katsuji; Nagasawa Katsumi; Hashiura, Sintaro

2000-01-01

Onagawa nuclear power plant developed a system for chemistry management of prevention and preservation of power plant. It is able to early detection of data change for prevention of plant. The system supports management of chemical custodian and consists of four parts such as management of water quality of plant , management of liquid waste, management of vapor waste and estimation of performance of chemical equipment. The system has three functions: management of operation, estimation of omen and examination of origin. The function of management of operation supports the routine inspection of chemical custodian by increasing efficiency of analytical and process data collection, practical use of data,, accuracy of data and rapid analysis. Estimation function of omen observes data fetched via online during 24 hr, indicates the small primary change and determines the origins. Examination function of origin supports their quick correspondences at accident and certificates the detailed origins. Histories of development of the system, business systemization, system construction, system functions are explained.The diagram of background of system development, system construction, management functions, verification of analytical data, automatic continuos monitoring diagram, screen of detection of abnormal phenomena, classified diagram of origins for change of water quality in reactor were developed. (S.Y.)

Efforts to improve safety and reliability of nuclear power plants in Kyushu Electric Power

International Nuclear Information System (INIS)

Yamamoto, Satoshi

2014-01-01

After the Fukushima accident, Kyushu Electric Power Co. took emergency safety measures requested by government to ensure power supply, coolant supply pumps and cooling water so as to keep cooling fuels in the reactor and spent fuel storage pool in case of losses of ordinary cooling capability caused by earthquake and tsunami. In order to improve safety and reliability of nuclear power plants, further efforts based on lessons learned from the Fukushima accident had been made to diversify corresponding equipment of safety measures in terms of prevention of core damage, prevention of containment failure, mitigation of radioactive materials release, cooling of spent fuel pit and ensurance of power supply, and to enhance emergency response capability so as to make operational management more complete. Additional safety measures applicable to new regulatory requirements against severe accidents were in progress. This article introduced details of such activities. (T. Tanaka)

Nuclear power and heating plants in the electric power system. Part I

International Nuclear Information System (INIS)

Kalincik, L.

1975-01-01

Procedures used and results obtained in the following works are described: Incorporation of the nuclear power plants in the power system in the long term perspective; physical limitations on the WWER 440 reactor power changes during fuel campaigns; evaluation of the consumption and start-up characteristics of WWER type nuclear power plants (2x440 MWe); evaluation of refuelling campaigns distribution of nuclear power plant units with regard to comprehensive control properties of nuclear power plants; the possibilities are investigated of the utilization of the WWER type reactor for heat supply in Czechoslovakia. (author)

Bringing data about all nuclear power plants of the world to young people

International Nuclear Information System (INIS)

Stritar, Andrej

2001-01-01

Nuclear Training Centre in Ljubljana with its Information Centre has during the years developed several methods for presenting to general public the importance of nuclear power in today's World. Since some four years ago we have as an exhibit the World map with the hard wired LEDs representing each and every operating power reactor. It proved to be very effective as it gives the visitor a visual impression about the magnitude of that type of power source. Similar information we are also maintaining at our WWW home page http://www2.iis.si/~icjt/plants/ and http://www2.iis.si/~icjt/nukestat/ In parallel we have developed our own data base of all nuclear power plants of the World. We are permanently collecting data from all available sources like IAEA PRIS, INSC in Argonne or NucNet. To make these data even better understandable to general public but also to make them easily accessible to professionals, we have developed a special presentation system, very suitable for info centres and for distribution on CD ROMs. The basis of the system is an interactive map of the World, which can be easily rotated and zoomed in or out with the mouse. Each nuclear site is represented by a small icon, which is also an entry into more detailed data. For each site the user can see the detailed map, basic technical data about the site, photo if available and technical data about each unit on site. There are also summary data available about each nuclear country in a graphical form. Special attraction is an on-line display of the accumulated operating time of all nuclear power plants (currently about 9600 years), which is being updated every second. Similar display is available for each country. There are also summary data about the power and production at each continents and for each nuclear power country of the world, Special attraction is an on-line display of the accumulated operating time of all nuclear power plants (currently about 9600 years), which is being updated every second

Romanian achievement in hydro-power plants

International Nuclear Information System (INIS)

Cardu, M.; Bara, T.

1998-01-01

This paper briefly deals with the achievements relating to Hydro-electric Power Plants within the process of development of the National Power System in Romania. Also presented is the Romanian industry contribution to hydro-electrical power plant equipment manufacturing. (author)

Power Oscillation Damping from VSC-HVDC Connected Offshore Wind Power Plants

DEFF Research Database (Denmark)

Zeni, Lorenzo; Eriksson, Robert; Goumalatsos, Spyridon

2016-01-01

The implementation of power oscillation damping service on offshore wind power plants connected to onshore grids by voltage-source-converter-based high voltage direct current transmission is discussed. Novel design guidelines for damping controllers on voltage-source converters and wind power plant...... regarding real wind power plants are discussed: 1) robustness against control/communication delays; 2) limitations due to mechanical resonances in wind turbine generators; 3) actual capability of wind power plants to provide damping without curtailing production; and 4) power-ramp rate limiters....... controllers are derived, using phasor diagrams and a test network model and are then verified on a generic power system model. The effect of voltage regulators is analyzed, which is important for selecting the most robust damping strategy. Furthermore, other often disregarded practical implementation aspects...

Countermeasure to plant life management of the nuclear power plants out of Japan

International Nuclear Information System (INIS)

1999-01-01

Some investigations on countermeasure to plant life management of the nuclear power plants were begun since beginning of 1990s under cooperation with Ministry of International Trade and Industry and all electric power companies under consideration of recent state on abroad and at concept of preventive conservation implementation against the plant life management. As a result, the Tokyo Electric Power Company, the Kansai Electric Power Company and the Japan Atomic Power Company settled each program on countermeasure to plant life management of the Fukushima-1 Power Plant, the Mihama-1 Power Plant and the Tsuruga-1 Power Plant, respectively, which were reported to the Atomic Energy Safety Commission to issue on February, 1999, after deliberation in the Adviser Group of Ministry of International Trade and Industry. Such investigations on countermeasure to the plant life management are also conducted out of Japan in parallel to those in Japan, which contain programs reflecting states of operation and maintenance of nuclear power plants and atmosphere around atomic energy in each country. Here were described on some present states of the countermeasures to plant life management in U.S.A., France, Germany, Sweden, England and so forth. (G.K.)

Psychological empowerment in French nuclear power plants

International Nuclear Information System (INIS)

Fillol, Charlotte

2011-01-01

Since the eighties, nuclear safety has been discussed in organizational studies and constitutes nowadays a specific stream with several standpoints. Regarding the reliability of nuclear plants, the nuclear safety literature has emphasized on the crucial role of individuals and human factors. Especially, some researchers have noticed rule breaking behavior and the impact of individual self-confidence on the behavior; but without deepening their analyses. As high self-esteem and confidence, i.e. psychological empowerment, naturally lead to innovation and rule breaking, the behavior can be analyzed, in such a regulated industry, as opposite to safety. Thus, this article aims at explaining the roots and discernable features of the observed psychological empowerment. Methods include an in-depth qualitative study in 4 nuclear power plants owned by Electricite de France (EDF), the French national nuclear power operator. Focused on the leading team of the plant, the set of data is composed of 35 interviews, 6 weeks of non-participant observation and internal documents. The content analysis has revealed two main pillars of psychological empowerment. On the first hand, the strong professional identity developed at the opening of the plants is based on initiative and risk-taking. In some ways, this professional identify fostered by commitment to a demanding job and the team, influences behavior more than do professional rules. On the second hand, the management discourse is perceived as ambiguous towards the strict application of the rules and tacitly legitimizes rule breaking behavior. This article details and exemplifies these phenomena and discusses the implications. (author)

Changes in control room at Swedish nuclear power plants

International Nuclear Information System (INIS)

Kecklund, Lena

2005-09-01

The Swedish nuclear power plants were commissioned during a period between 1972 and 1985 and the instrumentation and control equipment are basically from that period. For several years there have been plans made for changes in all the nuclear power plants and to a certain extent the changes in control equipment and monitoring rooms have also been implemented. The object of this project was to make a comprehensive review of the changes in control room design implemented in the Swedish nuclear power plants and to describe how the MTO- (Man-Technology-Organisation) and (Man-Machine-Interface) -issues have been integrated in the process. The survey is intended to give an overall picture of the changes in control room design and man-machine-interface made in the Swedish control rooms, in order to get a deeper knowledge of the change management process and its results as well as of the management of MTO-issues in these projects. The units included in this survey are: Oskarhamn reactor 2 and 3; Ringhals reactor 2, 3 and 4; Forsmark reactor 1, 2 and 3. The Oskarshamn 1 unit has not been included in this report as it has recently undergone an extensive modernisation program as well as a detailed inspection by the SKI (Swedish Nuclear Power Inspectorate). At Ringhals 2 the modernisation work is carried out at present and the unit is also subjected to extensive inspection activities carried out by SKI and is therefore not part of this survey. This report also includes a short description of relevant standards and requirements. Then follows a presentation of the results of the plant survey, presented as case studies for three companies OKG, Ringhals and FKA. Control room changes are summarized as well as the results on specific MTO issues which has been surveyed. In all the power companies there is a joint way of working with projects concerning plant modifications. This process is described for each company separately. In the concluding of the report the strengths and

Overview of IAEA guidelines for fire safety inspection and operation in nuclear power plants

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

In 1992, the International Atomic Energy Agency began an ambitious project on fire safety in nuclear power plants. The purpose of this ongoing project is to provide specific guidance on compliance with the requirements set forth through the IAEA Nuclear Safety Standards program established in 1974. The scope of the Fire Safety project encompasses several tasks, including the development of new standards and guidelines to assist Member States in assessing the level of fire safety in existing plants. Five new Safety Practices, one new Safety Guide and a Technical Document have been developed for use by the fire safety community. The primary intent of these new documents is to provide detailed guidance and a consistent format for the assessment of the overall level of fire safety being provided in existing nuclear power plants around the world and especially in developing countries. Sufficient detail is provided in the Safety Guide and Safety Practices to allow technically knowledgeable plant personnel, outside consultants or other technical experts to assess the adequacy of fire safety within the plant facilities. This paper describes topics addressed by each of the IAEA Fire Safety documents and discussed the relationship of each document to others in the series. (author)

Emergency power systems at nuclear power plants

International Nuclear Information System (INIS)

1982-01-01