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)

Design of a fault diagnosis system for next generation nuclear power plants

International Nuclear Information System (INIS)

Zhao, K.; Upadhyaya, B.R.; Wood, R.T.

2004-01-01

A new design approach for fault diagnosis is developed for next generation nuclear power plants. In the nuclear reactor design phase, data reconciliation is used as an efficient tool to determine the measurement requirements to achieve the specified goal of fault diagnosis. In the reactor operation phase, the plant measurements are collected to estimate uncertain model parameters so that a high fidelity model can be obtained for fault diagnosis. The proposed algorithm of fault detection and isolation is able to combine the strength of first principle model based fault diagnosis and the historical data based fault diagnosis. Principal component analysis on the reconciled data is used to develop a statistical model for fault detection. The updating of the principal component model based on the most recent reconciled data is a locally linearized model around the current plant measurements, so that it is applicable to any generic nonlinear systems. The sensor fault diagnosis and process fault diagnosis are decoupled through considering the process fault diagnosis as a parameter estimation problem. The developed approach has been applied to the IRIS helical coil steam generator system to monitor the operational performance of individual steam generators. This approach is general enough to design fault diagnosis systems for the next generation nuclear power plants. (authors)

Vibrations measurement at the Embalse nuclear power plant's electrical generator

International Nuclear Information System (INIS)

Salomoni, R.C.; Belinco, C.G.; Pastorini, A.J.; Sacchi, M.A.

1987-01-01

After the modifications made at the Embalse nuclear power plant's electrical generator to reduce its vibration level produced by electromagnetic phenomena, it was necessary to perform measurements at the new levels, under different areas and power conditions. To this purpose, a work was performed jointly with the 'Vibrations Team' of the ANSALDO Company (the generator constructor) and the Hydrodynamic Assays Division under the coordination and supervision of the plant's electrical maintenance responsible. This paper includes the main results obtained and the instrumentation criteria and analysis performed. (Author)

Trend analyses of the emergency diesel generator problem events in Japanese and U.S. nuclear power plants

International Nuclear Information System (INIS)

Shimada, Yoshio

2011-01-01

Up to 2009, the author and a colleague conducted trend analyses of problem events related to main generators, emergency diesel generators, breakers, motors and transformers which are more likely to cause problems than other electric components in nuclear power plants. Among the electric components with high frequency of defect occurrence, i.e., emergency diesel generators, several years have passed since the last analyses. These are very important components needed to stop a nuclear reactor safely and to cool it down during external power supply loses. Then trend analyses were conducted for the second time. The trend analyses were performed on 80 problem events with emergency diesel generators which had occurred in U.S. nuclear power plants in the five years from 2005 through 2009 among events reported in the Licensee Event Reports (LERs: event reports submitted to NRC by U.S. nuclear power plants) which have been registered in the nuclear information database of the Institute of Nuclear Safety System, Inc. (INSS) , as well as 40 events registered in the Nuclear Information Archives (NUCIA), which occurred in Japanese nuclear power plants in the same time period. It was learned from the trend analyses of the problem events with emergency diesel generators that frequency of defect occurrence are high in both Japanese and US plants during plant operations and functional tests (that is, defects can be discovered effectively in advance), so that implementation of periodical functional tests under plant operation is an important task for the future. (author)

Next Generation Nuclear Plant Materials Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

G. O. Hayner; E.L. Shaber

2004-09-01

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant

Energy Technology Data Exchange (ETDEWEB)

John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

2004-06-01

This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant

International Nuclear Information System (INIS)

Chan, Yea-Kuang; Tsai, Yu-Ching

2017-01-01

The objective of this study is to develop a turbine cycle model using the multiple regression approach to estimate the turbine-generator output for the Chinshan Nuclear Power Plant (NPP). The plant operating data was verified using a linear regression model with a corresponding 95% confidence interval for the operating data. In this study, the key parameters were selected as inputs for the multiple regression based turbine cycle model. The proposed model was used to estimate the turbine-generator output. The effectiveness of the proposed turbine cycle model was demonstrated by using plant operating data obtained from the Chinshan NPP Unit 2. The results show that this multiple regression based turbine cycle model can be used to accurately estimate the turbine-generator output. In addition, this study also provides an alternative approach with simple and easy features to evaluate the thermal performance for nuclear power plants.

Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Chan, Yea-Kuang; Tsai, Yu-Ching [Institute of Nuclear Energy Research, Taoyuan City, Taiwan (China). Nuclear Engineering Division

2017-03-15

The objective of this study is to develop a turbine cycle model using the multiple regression approach to estimate the turbine-generator output for the Chinshan Nuclear Power Plant (NPP). The plant operating data was verified using a linear regression model with a corresponding 95% confidence interval for the operating data. In this study, the key parameters were selected as inputs for the multiple regression based turbine cycle model. The proposed model was used to estimate the turbine-generator output. The effectiveness of the proposed turbine cycle model was demonstrated by using plant operating data obtained from the Chinshan NPP Unit 2. The results show that this multiple regression based turbine cycle model can be used to accurately estimate the turbine-generator output. In addition, this study also provides an alternative approach with simple and easy features to evaluate the thermal performance for nuclear power plants.

Steam generator for use in nuclear power plants

International Nuclear Information System (INIS)

Cella, A.

1980-01-01

An improved steam generator is described for use in a nuclear power plant of the pressurized water type in which a turbine generator is driven by the steam output of the steam generator to provide electrical power therefrom. The improvement comprises providing a vertically movable grid structure vertically extending within the interior of the lower housing portion of the steam generator through which individual tubes comprising a vertically extending tube bundle extend. The tube bundle has a tube sheet at one end thereof supporting the tube bundle for the tubes extending through the tube sheet in flow through communication with a heat exchange fluid inlet. The grid structure defines grid apertures therein through which the individual tubes extend with each of the grid apertures being in surrounding relationship with a portion of an associated one of the tubes. The grid structure is movable for a predetermined vertical extent, such as by hydraulic means, such as a piston, along the tubes for vertically displacing the means defining the grid apertures by a sufficient amount for removing the previously surrounded portion of each of the tubes from the associated grid apertures whereby an enhanced reading of the condition of the tubes at the previously surrounded portion is enabled. The steam generator may comprise vertically assemblable modules which are removably mounted together in sealing relationship, with the modules comprising a base module, a tube bundle module removably mountable on the base module in sealing relationship therewith and an uppermost drier module removably mountable on the tube bundle module in sealing relationship therewith whereby ready access to removal of the tube bundle module in situ from the nuclear power plant steam generator is facilitated

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.)

Status of the Monticello nuclear generating plant lead plant license renewal program

International Nuclear Information System (INIS)

Pickens, T.A.

1992-01-01

In 1988, the Monticello nuclear generating plant was chosen by the US Department of Energy through Sandia National Laboratories and the Electric Power Research Institute to serve as the lead boiling water reactor in the lead plant license renewal program. The purpose of the lead plant license renewal program is to provide insights during the development of and to demonstrate the license renewal regulatory process with the US Nuclear Regulatory Commission (NRC). The work being performed in three phases: (1) preparation of the technical basis for license renewal; (2) development of the technical basis into a formal license renewal application; and (3) review of the application by the NRC. This paper discusses the systems and structures identified as important to license renewal in accordance with 10CFR54 as well as the plant documents and programs that were used in going through the identification process. The systems and structures important to license renewal will then provide insights into how structures and components were identified that are required to be evaluated for aging, the elements of the aging evaluations, and the effective programs used to manage potentially significant aging

The nuclear power generation

International Nuclear Information System (INIS)

Serres, R.

1999-01-01

The French nuclear generating industry is highly competitive. The installations have an average age of fifteen years and are half way through their expected life. Nuclear power accounts for 70% of the profits of the French generating company, EDF. Nuclear generation has a minimal effect on the atmosphere and France has a level of CO 2 emissions, thought to be the main cause of the greenhouse effect, half that of Europe as a whole. The air in France is purer than in neighbouring countries, mainly because 75% of all electrical power is generated in nuclear plants and 15% in hydroelectric stations. The operations and maintenance of French nuclear power plants in the service and distribution companies out of a total of 100 000 employees in all, 90 % of whom are based in mainland France. (authors)

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.)

A qualitative model construction method of nuclear power plants for effective diagnostic knowledge generation

International Nuclear Information System (INIS)

Yoshikawa, Shinji; Endou, Akira; Kitamura, Yoshinobu; Sasajima, Munehiko; Ikeda, Mitsuru; Mizoguchi, Riichiro.

1994-01-01

This paper discusses a method to construct a qualitative model of a nuclear power plant, in order to generate effective diagnostic knowledge. The proposed method is to prepare deep knowledge to be provided to a knowledge compiler based upon qualitative reasoning (QR). Necessity of knowledge compilation for nuclear plant diagnosis will be explained first, and conventionally-experienced problems in qualitative reasoning and a proposed method to overcome this problem is shown next, then a sample procedure to build a qualitative nuclear plant model is demonstrated. (author)

Optimization for set-points and robust model predictive control for steam generator in nuclear power plants

International Nuclear Information System (INIS)

Osgouee, Ahmad

2010-01-01

Full Text: Nuclear power plants will be needed for future energy demands, which are expected to grow at different rates around the world. Lower operating cost is one of the major benefits of nuclear power plants over fossil power plants. Also, the plant availability is a key factor to economic index of a nuclear power plant. The opportunities for building new nuclear power plants around the world will depend on the need for clean energy with zero, or minimal emissions to support healthy communities, supply reliable energy with stable prices, and issues related to global warming and climate change. Compared to other types of power plants, nuclear power plants are preferred for their numerous advantages, including low operating costs, emission free operation with no smog, no acid rain, and no effect on global warming. Economic feasibility of a nuclear power plant requires for smooth and uninterrupted plant operation during electrical power demand variations. The steam generator (SG) in a nuclear power plant plays an important role in cooling of the reactor, balancing energy between reactor and turbine and producing steam for the turbine-generators. SG acts as an additional safety barrier between the nuclear reactor and the outside world also. As a result, control of the water inventory in the SG is very important to ensure continuous cooling of the nuclear reactor core, plant protection and at the same time, to prevent the SG tubes and turbine blades failure. A review of past nuclear power plant operation experiences indicates that unplanned reactor trips due to steam generator level (SGL) control have been significant contributors to plant unavailability. During low power operation, the level control is complicated by the thermal reverse effects known as 'shrink and swell'. Manual operator intervention to the SGL control system at low reactor power and to the unit upset conditions has been identified as an operator response in most nuclear power plants. In spite of

Counter Action Procedure Generation in an Emergency Situation of Nuclear Power Plants

Science.gov (United States)

Gofuku, A.

2018-02-01

Lessons learned from the Fukushima Daiichi accident revealed various weak points in the design and operation of nuclear power plants at the time although there were many resilient activities made by the plant staff under difficult work environment. In order to reinforce the measures to make nuclear power plants more resilient, improvement of hardware and improvement of education and training of nuclear personnel are considered. In addition, considering the advancement of computer technology and artificial intelligence, it is a promising way to develop software tools to support the activities of plant staff.This paper focuses on the software tools to support the operations by human operators and introduces a concept of an intelligent operator support system that is called as co-operator. This paper also describes a counter operation generation technique the authors are studying as a core component of the co-operator.

Reducing Risk for the Next Generation Nuclear Plant

Energy Technology Data Exchange (ETDEWEB)

John M. Beck II; Harold J. Heydt; Emmanuel O. Opare; Kyle B. Oswald

2010-07-01

The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.

Reducing Risk for the Next Generation Nuclear Plant

International Nuclear Information System (INIS)

Beck, John M. II; Heydt, Harold J.; Opare, Emmanuel O.; Oswald, Kyle B.

2010-01-01

The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.

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.)

Common cause failure rate estimates for diesel generators in nuclear power plants

International Nuclear Information System (INIS)

Steverson, J.A.; Atwood, C.L.

1982-01-01

Common cause fault rates for diesel generators in nuclear power plants are estimated, using Licensee Event Reports for the years 1976 through 1978. The binomial failure rate method, used for obtaining the estimates, is briefly explained. Issues discussed include correct classification of common cause events, grouping of the events into homogeneous data subsets, and dealing with plant-to-plant variation

Thermo hydrodynamical analyses of steam generator of nuclear power plant

International Nuclear Information System (INIS)

Petelin, S.; Gregoric, M.

1984-01-01

SMUP computer code for stationary model of a U-tube steam generator of a PWR nuclear power plant was developed. feed water flow can enter through main and auxiliary path. The computer code is based on the one dimensional mathematical model. Among the results that give an insight into physical processes along the tubes of steam generator are distribution of temperatures, water qualities, heat transfer rates. Parametric analysis permits conclusion on advantage of each design solution regarding heat transfer effects and safety of steam generator. (author)

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.)

Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant

Energy Technology Data Exchange (ETDEWEB)

Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

2009-03-01

The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

Load following generation in nuclear power plants by latent thermal energy storage

International Nuclear Information System (INIS)

Abe, Yoshiyuki; Takahashi, Yoshio; Kamimoto, Masayuki; Sakamoto, Ryuji; Kanari, Katsuhiko; Ozawa, Takeo

1985-01-01

The recent increase in nuclear power plants and the growing difference between peak and off-peak demands imperatively need load following generation in nuclear power plants to meet the time-variant demands. One possible way to resolve the problem is, obviously, a prompt reaction conrol in the reactors. Alternatively, energy storage gives another sophisticated path to make load following generation in more effective manner. Latent thermal energy storage enjoys high storage density and allows thermal extraction at nearly constant temperature, i.e. phase change temperature. The present report is an attempt to evaluate the feasibility of load following electric power generation in nuclear plants (actually Pressurized Water Reactors) by latent thermal energy storage. In this concept, the excess thermal energy in the off-peak period is stored in molten salt latent thermal energy storage unit, and additional power output is generated in auxiliary generator in the peak demand duration using the stored thermal energy. The present evaluation gives encouraging results and shows the primary subject to be taken up at first is the compatibility of candidate storage materials with inexpensive structural metal materials. Chapter 1 denotes the background of the present report, and Chapter 2 reviews the previous studies on the peak load coverage by thermal energy storage. To figure out the concept of the storage systems, present power plant systems and possible constitution of storage systems are briefly shown in Chapter 3. The details of the evaluation of the candidate storage media, and the compilation of the materials' properties are presented in Chapter 4. In Chapter 5, the concept of the storage systems is depicted, and the economical feasibility of the systems is evaluated. The concluding remarks are summarized in Chapter 6. (author)

Certification of materials for steam generator condensor and regeneration heat exchanger for nuclear plant

International Nuclear Information System (INIS)

Stevanovicj, M.V.; Jovashevicj, V.J.; Jovashevicj, V.D.J.; Spasicj, Zh.Lj.

1977-01-01

In the construction of a nuclear power plant almost all known materials are used. The choice depends on working conditions. In this work standard specifications of contemporary materials that take part in larger quantities in the following components of the secondary circuit of PWR-type nuclear power plant are proposed: steam generator with moisture separator, condensor and regenerative heat eXchanger

Nuclear power plants in the world

International Nuclear Information System (INIS)

2008-01-01

The Japan Atomic Industrial Forum, Inc. (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 2007/2008 was made up on bases of answers on questionnaires from electric power companies and other nuclear organizations around the world by JAIF. This report is comprised of 18 items, and contains generating capacity of the plants; effect of the Niigata-ken chuetsu-oki earthquake; 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.)

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2004-01-01

The Japan Atomic Industrial Forum, Inc. (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 2003 was made up on bases of answers on questionnaires from 81 electric power companies and other nuclear organizations in 33 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.)

Artificial earthquake generation for nuclear power plant design

International Nuclear Information System (INIS)

King, A.C.Y.; Chen, C.

1977-01-01

The time history method has been one of the analytical tools applied in the seismic resistant design of nuclear power plants. The time histories used are required to be consistent with the specified design Spectra. Since the spectra of recorded strong motion earthquake or conventionally generated artificial time history have local peaks and valleys, iteration procedures must be applied to generate the artificial time history with desired spectra. The paper describes a detailed method for generating a time history which is consistent with a specified design spectra. There are several advantages of this method described herein. First of all, frequency content of the time history is well under control. Secondly, if one wishes to generate the three components of an earthquake at one site, the inherent nature of this method will make the correlations among these three components to simulate closely the actual recorded time histories. Thirdly, a single time history can be generated to match a spectra for different damping values. (auth.)

Determination of leveled costs of electric generation for gas plants, coal and nuclear

International Nuclear Information System (INIS)

Alonso V, G.; Palacios H, J.C.; Ramirez S, J.R.; Gomez, A.

2005-01-01

The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

Nuclear heat generating plants - technical concepts and market potentials. Chapter 11

International Nuclear Information System (INIS)

Hasenkopf, O.; Erhard, W.D.; Nonnenmacher, A.; Hanselmann, M.

1988-01-01

Within the framework of a case study under the Federal Ministry of Research and Technology project 'Nuclear heat generating plants - technological concepts and market potentials', the possible applications of such plants were studied giving the district heat supply network of the Technische Werke der Stadt Stuttgart AG (Technical Works of the City of Stuttgart, Inc.) as an example. The use of district heating systems concentrated specifically on areas identified for economical supply because of their topographical position, existing heat density, distance from power plants, and a reasonable delimination from the available gas network. Based on the results of optimization calculations made by the Stuttgart Institute for Nuclear Technology and Energy Conversion, the required investment capital can be estimated as a function of the amount of fuel savings under the Stuttgart case study. (orig./UA) [de

Design of nuclear power generation plants adopting model engineering method

International Nuclear Information System (INIS)

Waki, Masato

1983-01-01

The utilization of model engineering as the method of design has begun about ten years ago in nuclear power generation plants. By this method, the result of design can be confirmed three-dimensionally before actual production, and it is the quick and sure method to meet the various needs in design promptly. The adoption of models aims mainly at the improvement of the quality of design since the high safety is required for nuclear power plants in spite of the complex structure. The layout of nuclear power plants and piping design require the model engineering to arrange rationally enormous quantity of things in a limited period. As the method of model engineering, there are the use of check models and of design models, and recently, the latter method has been mainly taken. The procedure of manufacturing models and engineering is explained. After model engineering has been completed, the model information must be expressed in drawings, and the automation of this process has been attempted by various methods. The computer processing of design is in progress, and its role is explained (CAD system). (Kako, I.)

The generation characteristics of solid radioactive wastes in the KEPCO nuclear power plants

International Nuclear Information System (INIS)

Shon, Soon Hwan; Kang, Duck Won; Kim, Hee Keun

1991-01-01

Solid radwastes generation trend and characteristics were discussed for nuclear power plants in KEPCO. Each plant has a specific tendency of solid radwastes generation due to the plant characteristics. The total volume of solid radwastes generated from nine power plants was accumulated in 23,012 drums by the end of 1989. The average annual volume per unit was about 670 drums. The solid radwaste mostly consisted of solidified concentrates and contaminated trash. The contaminated trash has been the major portion of the solid radwastes since 1982. The volume of the contaminated trash was dependent on the availability factor and period of overhaul. Therefore, the contaminated trash was considered to be a prime target for the solid radwastes minimization plan

General design criteria for diesel-generator sets for nuclear power plants

International Nuclear Information System (INIS)

Rangarao, G.

1975-01-01

The design criteria for diesel-generators for nuclear power plants are examined. Applicable standards, loading, design performance, and characteristics to be considered in the selection of diesel-generator set and its auxiliary system are discussed. Also, engineered safety features loads together with loss of power safe shutdown loads and their starting sequence, analysis of voltage and frequency response and the diesel-generator ability to start various load blocks successfully to meet the reactor emergency core cooling requirements are discussed

Situation of nuclear power generation in Europe

International Nuclear Information System (INIS)

Toukai, Kunihiro

2003-01-01

Nuclear power plants began to be built in Europe in the latter half of 1960. 146 plants are operating and generating about 33% of total power in 2002. France is top of Europe and operating 59 plants, which generate about 75% of power generation in the country. Germany is second and 30%. England is third and 30%. However, Germany decided not to build new atomic power plant in 2000. Movement of non-nuclear power generation is decreasing in Belgium and Switzerland. The liberalization of power generation decreased the wholesale price and BE Company in England was financial difficulties. New nuclear power generation is planning in Finland and France. (S.Y.)

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

Energy Technology Data Exchange (ETDEWEB)

John Collins

2009-01-01

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

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.)

The human factors issue in the next generation nuclear plants

International Nuclear Information System (INIS)

Noviello, L.; Bolognini, G.; Nobile, M.

1992-01-01

The national Energy Plan approved by the Italian Government in 1988, soon after the public referendum on nuclear issues held in the wake of the Chernobyl accident, requested the start of a research program to study next generation nuclear plants. These new reactors should feature some important and innovative characteristics to have a chance to be considered for future constructions, should the politicians decide the conditions for such a step are again re-established in Italy. The most important of these characteristics is certainly the fact that no evaluation nor land set a-side shall be required even in case of the most severe conceivable accident. This challenging objective should be reached through: a) the simplification of the nuclear plant as a whole b) the extensive use of passive components and/or inherent safety features in the design of the engineering safeguard systems c) a containment designed to cope with any conceivable accident sequence without releasing any major quantity of radioactive products into the environment. d) the upgrading of the man-machine interface and the introduction of computerized aids both for operational and maintenance activities. This paper deals in particular with the improvements, described in point d), that aim at greatly reducing the probability of human errors, widely recognized as one of the most important aspects to be pursued to increase nuclear plant safety. (author)

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)

Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants

International Nuclear Information System (INIS)

Kuhlmann, A.; Adamsky, F.-J.

1965-01-01

In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Überwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [fr

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

Large-Scale Combined Heat and Power (CHP) Generation at Loviisa Nuclear Power Plant Unit 3

International Nuclear Information System (INIS)

Bergroth, N.

2010-01-01

Fortum has applied for a Decision in Principle concerning the construction of a new nuclear power plant unit (Loviisa 3) ranging from 2800-4600 MWth at its site located at the southern coast of Finland. An attractive alternative investigated is a co-generation plant designed for large-scale district heat generation for the Helsinki metropolitan area that is located approximately 75 km west of the site. The starting point is that the district heat generation capacity of 3 unit would be around 1 000 MWth.The possibility of generating district heat for the metropolitan area by Loviisa's two existing nuclear power plant units was investigated back in the 1980s, but it proved unpractical at the time. With the growing concern of the climate change and the subsequent requirements on heat and power generation, the idea is much more attractive today, when recognising its potential to decrease Finland's carbon dioxide emissions significantly. Currently the district heat generation in metropolitan area is based on coal and natural gas, producing some five to seven million tonnes of carbon dioxide emissions annually. Large-scale combined heat and power (CHP) generation at the 3 unit could cut this figure by up to four million tonnes. This would decrease carbon dioxide emissions by as much as six percent. In addition, large-scale CHP generation would increase the overall efficiency of the new unit significantly and hence, reduce the environmental impact on the local marine environment by cutting heat discharges into the Gulf of Nuclear energy has been used for district heating in several countries both in dedicated nuclear heating plants and in CHP generation plants. However, the heat generation capacity is usually rather limited, maximum being around 250 MWth per unit. Set against this, the 3 CHP concept is much more ambitious, not only because of the much larger heat generation output envisaged, but also because the district heating water would have to be transported over a

Effects of the accident at Mihama Nuclear Power Plant Unit 3 on the public's attitude to nuclear power generation

International Nuclear Information System (INIS)

Kitada, Atsuko

2005-01-01

As part of an ongoing public opinion survey regarding nuclear power generation, which started in 1993, a survey was carried out in the Kansai and Kanto regions two months after the accident at Unit 3 of the Mihama Nuclear Power Plant. In addition to analyzing the statistically significant changes that have taken place since the previous survey (taken in 2003), increase and decrease of the ratio of answers to all the questions related to nuclear power before and after the two accidents were compared in the case of the accidents which occurred in the Mihama Unit 3 and the JCO company's nuclear-fuel plant. In the Kansai region, a feeling of uneasiness about the risky character of nuclear power generation increased to some extent, while the public's trust in the safety of nuclear power plants decreased somewhat. After a safety-related explanation on ''Early detection of troubles'' and Accident prevention'' was given from a managerial standpoint, people felt a little less at ease than they had before. Uneasiness, however, did not increase in relation to the overall safety explanation given about the engineering and technical functioning of the plant. There was no significant negative effect on the respondents' evaluation of or attitude toward nuclear power generation. It was found that the people's awareness about the Mihama Unit 3 accident was lower and the effect of the accident on their awareness of nuclear power generation was more limited and smaller when compared with the case of the JCO accident. In the Kanto region, people knew less about the Mihama Unit 3 accident than those living in the Kansai region, and they remembered the JCO accident, the subsequent cover-up by Tokyo Electric Power Company, and the resulting power shortage better than those living in Kansai. This suggested that there was a little difference in terms of psychological distance in relation to the accidents an incidents depending on the place where the events occurred and the company which

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

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

Energy Technology Data Exchange (ETDEWEB)

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

The steam generator repair project of the Donald C. Cook Nuclear Plant, Unit 2

International Nuclear Information System (INIS)

White, J.D.

1993-01-01

Donald C. Cook Nuclear Plant Unit 2 is part of a two unit nuclear complex located in southwestern Michigan and owned and operated by the Indiana Michigan Power Company. The Cook Nuclear Plant is a pressurized water reactor (PWR) plant with four Westinghouse Series 51 steam generators housed in an ice condenser containment. This paper describes the program undertaken by Indiana Michigan Power and the American Electric Power Service Corporation (AEPSC) to repair the Unit 2 steam generators. (Both Indiana Michigan Power and AEPSC arc subsidiaries of American Electric Power Company, Incorporated (AEP). AEPSC provides management and technical support services to Indiana Michigan Power and the other AEP operating companies.) Eddy current examinations, in a series of refueling and forced outages between November 1983 and July 1986 resulted in 763 (5.6%) plugged tubes. In order to maintain adequate reactor core cooling, a limit of 10% is placed on the allowable percentage of steam generator tubes that can be removed from service by plugging. Additionally, sections of tubes were removed for metallurgical analysis and confirmed that the degradation was due to intergranular stress corrosion cracking. In developing the decision on how to repair the steam generators, four alternative actions were considered for addressing these problems: retubing in place, sleeving, operating at 80% reactor power to lower temperature and thus reduce the rate of corrosion, replacing steam generator lower assemblies

On the reliability of steam generator performance at nuclear power plants with WWER type reactors

International Nuclear Information System (INIS)

Styrikovich, M.A.; Margulova, T.Kh.

1974-01-01

The problem of ensuring reliable operation of steam generators in a nuclear power plant with a water-cooled, water-moderated reactor (WWER) was studied. At a nuclear power plant with a vertical steam generator (specifically, a Westinghouse product) the steam generator tubes were found to have been penetrated. Shutdown was due to corrosion disintegration of the austenitic stainless steel, type 18/8, used as pipe material for the heater surface. The corrosion was the result of the action of chlorine ions concentrated in the moisture contained in the iron oxide films deposited in low parts of the tube bundle, directly at the tube plate. Blowing through did not ensure complete removal of the film, and in some cases the construction features of the steam generator made removal of the film practically impossible. Replacement of type 18/8 stainless steel by other construction material, e.g., Inconel, did not give good results. To ensure reliable operation of vertical steam generators in domestic practice, the generators are designed without a low tube plate (a variant diagram of the vertical steam generator of such construction for the water-cooled, water-moderated reactor 1000 is presented). When low tube plates are used the film deposition is intolerable. For organization of a non-film regime a complex treatment of the feed water is used, in which the amount of complexion is calculated from the stoichmetric ratios with the composition of the feed water. It is noted that, if 100% condensate purification is used with complexon processing of the feed water to the generator, we can calculate the surface of the steam-generator heater without considering the outer placement on the tubes. In this the cost of the steam generator and all the nuclear power plants with WWER type reactors is decreased even with installation of a 100% condensate purification. It is concluded that only simultaneous solution of construction and water-regime problems will ensure relaible operation of

Soviet steam generator technology: fossil fuel and nuclear power plants

International Nuclear Information System (INIS)

Rosengaus, J.

1987-01-01

In the Soviet Union, particular operational requirements, coupled with a centralized planning system adopted in the 1920s, have led to a current technology which differs in significant ways from its counterparts elsewhere in the would and particularly in the United States. However, the monograph has a broader value in that it traces the development of steam generators in response to the industrial requirements of a major nation dealing with the global energy situation. Specifically, it shows how Soviet steam generator technology evolved as a result of changing industrial requirements, fuel availability, and national fuel utilization policy. The monograph begins with a brief technical introduction focusing on steam-turbine power plants, and includes a discussion of the Soviet Union's regional power supply (GRES) networks and heat and power plant (TETs) systems. TETs may be described as large central co-generating stations which, in addition to electricity, provide heat in the form of steam and hot water. Plants of this type are a common feature of the USSR today. The adoption of these cogeneration units as a matter of national policy has had a central influence on Soviet steam generator technology which can be traced throughout the monograph. The six chapters contain: a short history of steam generators in the USSR; steam generator design and manufacture in the USSR; boiler and furnace assemblies for fossil fuel-fired power stations; auxiliary components; steam generators in nuclear power plants; and the current status of the Soviet steam generator industry. Chapters have been abstracted separately. A glossary is included containing abbreviations and acronyms of USSR organizations. 26 references

Nuclear power generation

International Nuclear Information System (INIS)

Hirao, Katumi; Sato, Akira; Kaimori, Kimihiro; Kumano, Tetsuji

2001-01-01

Nuclear power generation for commercial use in Japan has passed 35 years since beginning of operation in the Tokai Nuclear Power Station in 1966, and has 51 machines of reactor and about 44.92 MW of total output of equipment scale in the 21st century. However, an environment around nuclear energy becomes severer at present, and then so many subjects to be overcome are remained such as increased unreliability of the public on nuclear energy at a chance of critical accident of the JCO uranium processing facility, delay of pull-thermal plan, requirement for power generation cost down against liberalization of electric power, highly aging countermeasure of power plant begun its operation as its Genesis, and so on. Under such conditions, in order that nuclear power generation in Japan survives as one of basic electric source in future, it is necessary not only to pursue safety and reliability of the plant reliable to the public, but also to intend to upgrade its operation and maintenance by positively adopting good examples on operational management method on abroad and to endeavor further upgrading of application ratio of equipments and reduction of generation cost. Here were outlined on operation conditions of nuclear power stations in Japan, and introduced on upgrading of their operational management and maintenance management. (G.K.)

78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2013-08-13

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-445 and 50-446; NRC-2013-0182] Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application for Amendment to Facility... Operating License Nos. NPF-87 and NPF-89 for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

Energy Technology Data Exchange (ETDEWEB)

R. Doug Hamelin; G. O. Hayner

2004-11-01

The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

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.

DIMOS: a new generation of nuclear power plant process monitoring systems

International Nuclear Information System (INIS)

Vlaminck, M. de; Gilliot, B.; Remacle, J.

1993-01-01

A new generation of nuclear power plant supervision systems is described, called DIMOS (DIstributed MOnitoring System). It was installed in August 1991 at the Doel nuclear power plant and is now monitoring reactors 1 and 2. The system represents one of the largest and most advanced process monitoring systems in operation. DIMOS has successfully provided the solution to the old system's limitations such as functional deficiencies, low response time, management and coherence of the data, maintenance costs, spare parts, and system availability. The use of the software development methodologies HOOD and ADA have not only allowed a rapid integration and installation of a robust system, but will also make further developments and improvements possible with maximum flexibility. (Z.S.) 2 figs

Nuclear power reactors of new generation

International Nuclear Information System (INIS)

Ponomarev-Stepnoi, N.N.; Slesarev, I.S.

1988-01-01

The paper presents discussions on the following topics: fuel supply for nuclear power; expansion of the sphere of nuclear power applications, such as district heating; comparative estimates of power reactor efficiencies; safety philosophy of advanced nuclear plants, including passive protection and inherent safety concepts; nuclear power unit of enhanced safety for the new generation of nuclear power plants. The emphasis is that designers of new generation reactors face a complicated but technically solvable task of developing highly safe, efficient, and economical nuclear power sources having a wide sphere of application

Limiting conditions for nuclear power plant competitiveness vs. fossil and wind plants

International Nuclear Information System (INIS)

Feretic, Danilo; Cavlina, Nikola

2010-01-01

The aim of this paper is to compare potential energy options for future electricity generation. The paper considers comparison of discounted total cost of electricity generated by nuclear power plant and by combined natural gas and wind plants, having in total equal electricity generation. Large uncertainty in the future fuel costs makes planning of optimal power generating mix very difficult to justify. Probabilistic method is used in the analysis which allows inclusion of uncertainties in future electricity generating cost prediction. Additionally, an informative functional relation between nuclear plant investment cost, natural gas price and wind plant efficiency, that determines competitive power generation between considered options, is also shown. Limiting conditions for nuclear power plant competitiveness vs. fossil and wind plants are presented. (authors)

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.)

Design of a partial inter-tube lancing system actuated by hydraulic power for type F model steam generator in nuclear power plant

International Nuclear Information System (INIS)

Kim, S. T.; Jeong, W. T.

2008-01-01

The sludge grown up in steam generators of nuclear power plants shortens the life-cycle of steam generators and reduces the output of power plants. So KHNP(Korea Hydro and Nuclear Power), the only nuclear power utility in Korea, removes it periodically using a steam generator lancing system during the outage of plants for an overhaul. KEPRI(Korea Electric Power Research Institute) has developed lancing systems with high pressured water nozzle for steam generators of nuclear power plants since 2001. In this paper, the design of a partial inter-tube lancing system for model F type steam generators will be described. The system is actuated without a DC motor inner steam generators because the motors in a steam generator make a trouble from high intensity of radioactivity as a break down

Multipurpose plant for simultaneous electricity and drinking water generation on the basis of nuclear fuel

International Nuclear Information System (INIS)

Kuenstle, K.

1978-01-01

After listing the available technologies for sea water desalination, the author discusses a) the problem of multi-stage distillation, b) the coupling of a thermal power plant and a sea water distillation plant and c) the dual-purpose plant with nuclear steam generation. He points out that the radiological considerations and regulations can be applied without modification to a nuclear interconnected system. The additional pathway for theoretical activity release is under sufficient control. Also discussed are the circuiting of the IRAN I and II plants, optimisation problems in dual-purpose plants, and chemically self-sufficient plants for simultaneous production of drinking water and raw materials from sea water. (GG) [de

78 FR 79709 - Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown...

Science.gov (United States)

2013-12-31

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2013-0283] Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of receipt; availability; public meeting; and request...

Disposal of Steam Generators from Decommissioning of PWR Nuclear Power Plants

International Nuclear Information System (INIS)

Walberg, Mirko; Viermann, Joerg; Beverungen, Martin; Kemp, Lutz; Lindstroem, Anders

2008-01-01

Amongst other materials remarkable amounts of radioactively contaminated or activated scrap are generated from the dismantling of Nuclear Power Plants. These scrap materials include contaminated pipework, fittings, pumps, the reactor pressure vessel and other large components, most of them are heat exchangers. Taking into account all commercial and technical aspects an external processing and subsequent recycling of the material might be an advantageous option for many of these components. The disposal of steam generators makes up an especially challenging task because of their measures, their weight and compared to other heat exchangers high radioactive inventory. Based on its experiences from many years of disposal of smaller components of NPP still in operation or under decommissioning GNS and Studsvik Nuclear developed a concept for disposal of steam generators, also involving experiences made in Sweden. The concept comprises transport preparations and necessary supporting documents, the complete logistics chain, steam generator treatment and the processing of arising residues and materials not suitable for recycling. The first components to be prepared, shipped and treated according to this concept were four steam generators from the decommissioning of the German NPP Stade which were removed from the plant and shipped to the processing facility during the third quarter of 2007. Although the plant had undergone a full system decontamination, due to the remaining contamination in a number of plugged tubes the steam generators had to be qualified as industrial packages, type 2 (IP-2 packages), and according to a special requirement of the German Federal Office for Radiation Protection a license for a shipment under special arrangement had to be applied for. The presentation gives an overview of the calculations and evidences required within the course of the IP-2 qualification, additional requirements of the competent authorities during the licensing procedure as

Challenges for new nuclear plants

International Nuclear Information System (INIS)

Bruschi, H.J.

2000-01-01

In the past 20 years, numerous new nuclear plant designs have been introduced in the hope of generating a mixture of features and benefits that generated enough enthusiasm amongst the utility industry decision makers to move forward with a new nuclear generation. Not only has there not been enough enthusiasm, there has been little interest in building new plants with advanced features, especially in the U.S. Compounding this predicament are the changing paradigms to which a new plant would be measured. The near hiatus on new plant orders is the clear cause of the significant consolidation in the nuclear industry. Regardless whether the disappearance of old-line nuclear companies is over or not, some paradigms for new generation designs are unmovable, while others are still under discussion as to their role in future plant designs. This paper will address those design goals that Westinghouse deems already having earned the rank of exemplar, and those still open to debate. Because it is my hope that this paper will lead to a fruitful discussion period, I will provide a list of what I feel are the champion design requirements, and those I consider the contenders. (author)

Next Generation Nuclear Plant GAP Analysis Report

Energy Technology Data Exchange (ETDEWEB)

Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

2008-12-01

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

Elecnuc. Nuclear power plants in the world. 1997

International Nuclear Information System (INIS)

Maubacq, F.; Tailland, C.

1997-04-01

This small booklet provides information about all type of nuclear power plants worldwide. It is based on the data taken from the CEA/DSE/SEE Elecnuc database. The content comprises: the 1996 highlights, the main characteristics of the different type of reactors in operation or under construction, the map of the French nuclear power plant sites, the worldwide status of nuclear power plants at the end of 1996, the nuclear power plants in operation, under construction or on order (by groups of reactor-types), the power capacity evolution of power plants in operation, the net and gross capacity of the power plants on the grid, the commercial operation and grid connection forecasts, the first achieved or expected power generation supplied by a nuclear reactor for each country and the power generation from nuclear reactors, the performance indicator of the PWR units in France, the trends of the power generation indicator worldwide, the nuclear power plants in operation, under construction, on order, planned, cancelled, decommissioned and exported worldwide, the schedule of steam generator replacements, and the MOX fuel plutonium recycling programme. (J.S.)

Nuclear power plants 1995 - a world survey

International Nuclear Information System (INIS)

Anon.

1996-01-01

The atw Statistics Report compiled by atw lists 428 nuclear power plants with 363 397 gross MWe in operation in 30 countries in late 1995. Another 62 units with 55 180 gross MWe were under construction in 18 countries. This adds up to a total of 490 units with an aggregate 418 577 MWe. In the course of 1995 four units in four countries started commercial operation. In the survey of electricity generation in 1995 for which no information was made available from China and Kasachstan, a total of 417 nuclear power plants were covered. In the year under review they generated an aggregate 2 282 614 GWH, which is 3.4% more than in the previous year. The highest nuclear generation again was recorded in the USA with 705 771 GWh, followed by France with 377 021 GWh. The Grohnde power station in Germany attained the maximum annual production figure of 11 359 GWh. The survey includes nine tables indicating the generating performance of each nuclear power plant, the development of electricity generation in nuclear plants, and status of nuclear power plants at the end of 1995 arranged by countries, types of reactors, and reactor manufacturers. (orig.) [de

Nuclear power plants in the world - 2010 edition

International Nuclear Information System (INIS)

2010-01-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2009 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2010/01/01, Worldwide status of nuclear power plants (12/31/2009), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2009, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear power plants by country at the end 2009, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2009, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2009, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2009, Long term shutdown units at 12/31/2009, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

Nuclear renaissance in Asia. Energy security and development of nuclear power generation system

International Nuclear Information System (INIS)

Nakasugi, Hideo

2009-01-01

The energy policy and strategy of development of nuclear power generation system of China, India and Korea are stated on the basis of use of light water reactors (LWRs). The conditions of power generation and introduction plans of nuclear energy of other Asian countries such as Vietnam, Thailand, Indonesia, Malaysia and Philippines are described. The power plant capacity of China increased from 50,500 MW in 2004, to 65,000 MW in 2005, and the target value is 40,000 MW of operating nuclear plants and 18,000 MW in building in 2020. China is lagging behind in peaceful use of nuclear energy technologies. A plan for the reform of nuclear industry and nuclear power generation projects of China are summarized. Total power plant capacity of India is 145,000 MW, but the nuclear plant capacity is 4,120 MW in 2008 and 63,000 MW of the target in 2032. Development of nuclear power, circumstance, and cooperation with other countries' industries are explained. 17,716 MW of nuclear power is in operation, 6,800 MW in building and 2,800 MW in the planning stage in Korea. History of development of national reactors and the subjects of development of the fourth generation reactor of Korea are stated. Management system of nuclear power plants in China, technical bases of nuclear power plants in China, development system of nuclear power generation in India, the conditions of power production of Korea in 2008, the capacity factor of Korea, Japan and world from 1998 to 2008, and comparison of nuclear industries in China, India and Korea are illustrated. (S.Y.)

Informing the next nuclear generation - how does the Ginna plant branch do it?

International Nuclear Information System (INIS)

Saavedra, A.

1995-01-01

Most of us are familiar with the latest advertising phrase, ''Our children are our future.'' This phrase has been used in so many instances - from concerns about waste, Social Security, and the federal deficit to drug abuse and violence. One more area can be added to the list and advertised nuclear power. Since the establishment of the Ginna plant branch (GPB) in 1992, our target audience has been the next nuclear generation (our children), but our vehicle for dissemination has been the current generation (the adults). Have you ever thought about how often your opinions affect the children you come in contact with? One of GPB's goals is to provide as much information as possible to teachers, neighbors, and civic organizations of our community so that there is a nuclear future that can be carried on by the next generation

Plant life extensions for German nuclear power plants? Controversial discussion on potential electricity price effects

International Nuclear Information System (INIS)

Matthes, Felix C.; Hermann, Hauke

2009-06-01

The discussions on electricity price effects in case of the plant life extension of German nuclear power plants covers the following topics: (1) Introduction and methodology. (2) Electricity generation in nuclear power plants and electricity price based on an empirical view: electricity generation in nuclear power plants and final consumption price for households and industry in the European Union; electricity generation in nuclear power plants and electricity wholesale price in case of low availability of nuclear power plants in Germany; comparison of electricity wholesale prices in Germany and France. (3) Model considerations in relation to electricity prices and nuclear phase-out. (4) Concluding considerations.

Steam Generator control in Nuclear Power Plants by water mass inventory

Energy Technology Data Exchange (ETDEWEB)

Dong Wei [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States); Doster, J. Michael [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States)], E-mail: doster@eos.ncsu.edu; Mayo, Charles W. [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States)

2008-04-15

Control of water mass inventory in Nuclear Steam Generators is important to insure sufficient cooling of the nuclear reactor. Since downcomer water level is measurable, and a reasonable indication of water mass inventory near steady-state, conventional feedwater control system designs attempt to maintain downcomer water level within a relatively narrow operational band. However, downcomer water level can temporarily react in a reverse manner to water mass inventory changes, commonly known as shrink and swell effects. These complications are accentuated during start-up or low power conditions. As a result, automatic or manual control of water level is difficult and can lead to high reactor trip rates. This paper introduces a new feedwater control strategy for Nuclear Steam Generators. The new method directly controls water mass inventory instead of downcomer water level, eliminating complications from shrink and swell all together. However, water mass inventory is not measurable, requiring an online estimator to provide a mass inventory signal based on measurable plant parameters. Since the thermal-hydraulic response of a Steam Generator is highly nonlinear, a linear state-observer is not feasible. In addition, difficulties in obtaining flow regime and density information within the Steam Generator make an estimator based on analytical methods impractical at this time. This work employs a water mass estimator based on feedforward neural networks. By properly choosing and training the neural network, mass signals can be obtained which are suitable for stable, closed-loop water mass inventory control. Theoretical analysis and simulation results show that water mass control can significantly improve the operation and safety of Nuclear Steam Generators.

Steam Generator control in Nuclear Power Plants by water mass inventory

International Nuclear Information System (INIS)

Dong Wei; Doster, J. Michael; Mayo, Charles W.

2008-01-01

Control of water mass inventory in Nuclear Steam Generators is important to insure sufficient cooling of the nuclear reactor. Since downcomer water level is measurable, and a reasonable indication of water mass inventory near steady-state, conventional feedwater control system designs attempt to maintain downcomer water level within a relatively narrow operational band. However, downcomer water level can temporarily react in a reverse manner to water mass inventory changes, commonly known as shrink and swell effects. These complications are accentuated during start-up or low power conditions. As a result, automatic or manual control of water level is difficult and can lead to high reactor trip rates. This paper introduces a new feedwater control strategy for Nuclear Steam Generators. The new method directly controls water mass inventory instead of downcomer water level, eliminating complications from shrink and swell all together. However, water mass inventory is not measurable, requiring an online estimator to provide a mass inventory signal based on measurable plant parameters. Since the thermal-hydraulic response of a Steam Generator is highly nonlinear, a linear state-observer is not feasible. In addition, difficulties in obtaining flow regime and density information within the Steam Generator make an estimator based on analytical methods impractical at this time. This work employs a water mass estimator based on feedforward neural networks. By properly choosing and training the neural network, mass signals can be obtained which are suitable for stable, closed-loop water mass inventory control. Theoretical analysis and simulation results show that water mass control can significantly improve the operation and safety of Nuclear Steam Generators

Integration of distributed plant process computer systems to nuclear power generation facilities

International Nuclear Information System (INIS)

Bogard, T.; Finlay, K.

1996-01-01

Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation ampersand control are evident from variations of design features

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)

From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant

Science.gov (United States)

Rachkov, V. I.; Kalyakin, S. G.; Kukharchuk, O. F.; Orlov, Yu. I.; Sorokin, A. P.

2014-05-01

Successful commissioning in the 1954 of the World's First nuclear power plant constructed at the Institute for Physics and Power Engineering (IPPE) in Obninsk signaled a turn from military programs to peaceful utilization of atomic energy. Up to the decommissioning of this plant, the AM reactor served as one of the main reactor bases on which neutron-physical investigations and investigations in solid state physics were carried out, fuel rods and electricity generating channels were tested, and isotope products were bred. The plant served as a center for training Soviet and foreign specialists on nuclear power plants, the personnel of the Lenin nuclear-powered icebreaker, and others. The IPPE development history is linked with the names of I.V. Kurchatov, A.I. Leipunskii, D.I. Blokhintsev, A.P. Aleksandrov, and E.P. Slavskii. More than 120 projects of various nuclear power installations were developed under the scientific leadership of the IPPE for submarine, terrestrial, and space applications, including two water-cooled power units at the Beloyarsk NPP in Ural, the Bilibino nuclear cogeneration station in Chukotka, crawler-mounted transportable TES-3 power station, the BN-350 reactor in Kazakhstan, and the BN-600 power unit at the Beloyarsk NPP. Owing to efforts taken on implementing the program for developing fast-neutron reactors, Russia occupied leading positions around the world in this field. All this time, IPPE specialists worked on elaborating the principles of energy supertechnologies of the 21st century. New large experimental installations have been put in operation, including the nuclear-laser setup B, the EGP-15 accelerator, the large physical setup BFS, the high-pressure setup SVD-2; scientific, engineering, and technological schools have been established in the field of high- and intermediate-energy nuclear physics, electrostatic accelerators of multicharge ions, plasma processes in thermionic converters and nuclear-pumped lasers, physics of compact

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

3D model of steam generator of nuclear power plant Krsko

International Nuclear Information System (INIS)

Ravnikar, I.; Petelin, S.

1995-01-01

The Westinghouse Electric Corporation D4 steam generator design was analyzed from a thermal-hydraulic point of view using the 3D PHOENICS computer code. Void fraction, velocity and enthalpy distributions were obtained in the U-tube riser. The boundary conditions of primary side were provided by SMUP 1D code. The calculations were carried out for present operating conditions of nuclear power plant Krsko. (author)

Nuclear power plants: 2009 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2010-01-01

At the turn of 2009/2010, nuclear power plants were available for energy supply in 30 countries of the world. A total of 437 nuclear power plants, which is one plant less than at the 2008/2009 turn, were in operation with an aggregate gross power of approx. 391 GWe and an aggregate net power, respectively, of 371 GWe. The available gross power of nuclear power plants did not changed noticeably from 2008 to the end of 2009. In total 2 nuclear generating units were commissioned in 2009. One NPP started operation in India and one in Japan. Three nuclear generating units in Japan (2) und Lithuania (1) were decomissioned in 2009. 52 nuclear generating units, i.e. 10 plants more than at the end of 2008, with an aggregate gross power of approx. 51 GWe, were under construction in 14 countries end of 2009. New or continued projects are notified from (number of new projects): China (+9), Russia (1), and South Korea (1). Some 84 new nuclear power plants are in the concrete project design, planning and licensing phases worldwide; on some of them, contracts have already been awarded. Another units are in their preliminary project phases. (orig.)

Nuclear power plants: 2008 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2009-01-01

At the turn of 2008/2009, nuclear power plants were available for energy supply in 31 countries of the world. A total of 438 nuclear power plants, which is one plant less than at the 2007/2008 turn, were in operation with an aggregate gross power of approx. 393 GWe and an aggregate net power, respectively, of 372 GWe. The available gross power of nuclear power plants didn't changed noticeabely from 2007 to the end of 2008. No nuclear generating unit was commissioned in 2008. One nuclear generating unit in the Slovak Republic was decomissioned in 2008. 42 nuclear generating units, i.e. 10 plants more than at the end of 2007, with an aggregate gross power of approx. 38 GWe, were under construction in 14 countries end of 2008. New or continued projects are notified from (in brackets: number of new projects): Bulgaria (2), China (5), South Korea (2), Russia (1), and the Slovak Republic (2). Some 80 new nuclear power plants are in the concrete project design, planning and licensing phases worldwide; on some of them, contracts have already been awarded. Another approximately 120 units are in their preliminary project phases. (orig.)

78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

Science.gov (United States)

2013-03-05

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0310; Docket Nos. 50-445 and 50-446; License Nos. NPF-87 and NPF-89] In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units... Nuclear Power Plant, Units 1 and 2 (CPNPP), and its Independent Spent Fuel Storage Installation Facility...

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

Energy Technology Data Exchange (ETDEWEB)

Pulkkinen, Urho [Technical Research Centre of Finland, Vuorimiehentie 5, SF-02150, Espoo (Finland)

1986-02-15

The operating experiences of 40 stand-by diesel generators at the Finnish and Swedish nuclear power plants have been analysed with special emphasis on the impact of the frequency of surveillance testing and of the test procedure on diesel generator reliability, the contribution of design, manufacturing, testing and maintenance errors and the potential and actual common cause failures, The results pf the analyses consisted both practical recommendations and mathematical reliability models and useful reliability data. (author)

From reliability to maintenance of emergency generator sets in nuclear plants

International Nuclear Information System (INIS)

Reyraud, Y.

1986-01-01

The particular conditions of operation of emergency generator sets in a nuclear energy plant induce to take up a strategy of supervision and of maintenance very different of the one recommended for production generator sets. Mechanical and thermal pulls are affected by the size of the set and the choice of rotation running in respect of the wanted power and the response time requirements for the security of nuclear reactor. Reliability studies are helpful to define the strategy of supervision tests. The importance of the number of starts with respect to the running time requires the introduction of the idea of equivalent hours for the definition of maintenance periods. The security of the equipment and the upholding of the reliability at a value close to the optimum impose rigorous choices and strict conditions of supervision and maintenance [fr

Site Selection and Characterization Status Report for Next Generation Nuclear Plant (NGNP)

International Nuclear Information System (INIS)

Holbrook, Mark

2007-01-01

In the near future, the US Department of Energy (DOE) will need to make important decisions regarding design and construction of the Next Generation Nuclear Plant (NGNP). One part of making these decisions is considering the potential environmental impacts that this facility may have, if constructed here at the Idaho National Laboratory (INL). The National Environmental Policy Act (NEPA) of 1969 provides DOE decision makers with a process to systematically consider potential environmental consequences of agency decisions. In addition, the Energy Policy Act of 2005 (Title VI, Subtitel C, Section 644) states that the 'Nuclear Regulatory Commission (NRC) shall have licensing and regulatory authority for any reactor authorized under this subtitle.' This stipulates that the NRC will license the NGNP for operation. The NRC NEPA Regulations (10 CFR Part 51) require tha thte NRC prepare an Environmental Impact Statement (EIS) for a permit to construct a nuclear power plant. The applicant is required to submit an Environmental report (ER) to aid the NRC in complying with NEPA.

Nuclear power generation and fuel cycle report 1997

International Nuclear Information System (INIS)

1997-09-01

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East

Nuclear power generation and fuel cycle report 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

Systematic generation of rules for nuclear power plant diagnostics

International Nuclear Information System (INIS)

Reifman, J.; Lee, J.C.

1988-01-01

The knowledge base of an expert system is generally represented by a set of heuristic rules derived from the expert's own experience and judgmental knowledge. These heuristic or production rules are cast as if (condition), then (consequence) statements, and represent, for nuclear power plant diagnostic systems, information connecting symptoms to failures. In this paper, the authors apply an entropy minimax pattern recognition algorithm to automate the process of extracting and encoding knowledge into a set of rules. Knowledge is extracted by recognizing patterns in plant parameters or symptoms associated with failures or transient events, and is encoded by casting the discovered patterns as production rules. The paper discusses how the proposed method can systematically generate rules that characterize failure of pressurizer components based on transient events analyzed with a pressurizer components based on transient events analyzed with a pressurizer water reactor simulator program

Managing nuclear predominant generating capacity

International Nuclear Information System (INIS)

Bouget, Y.H.; Carbonnier, D.

1999-01-01

The most common believe, associated with nuclear power plant, leads to the conclusion that it can only operate, as a base load plant. This observation can be reversed, by just looking at large generating capacity, using an important nuclear generation mix. Nuclear plants may certainly load follow and contribute to the grid frequency control. The French example illustrates these possibilities. The reactor control of French units has been customized to accommodate the grid requests. Managing such a large nuclear plant fleet requires to take various actions, ranging from a daily basis to a multi-annual prospective standpoint. The paper describes the various contributions leading to safe, reliable, well accepted and cost competitive nuclear plants in France. The combination of all aspects related to operations, maintenance scheduling, nuclear safety management, are presented. The use of PWR units carries considerable weight in economic terms, with several hundred million francs tied in with outage scheduling every year. This necessitates a global view of the entire generating system which can be mobilized to meet demand. There is considerable interaction between units as, on the one hand, they are competing to satisfy the same need, and, on the other hand, reducing maintenance costs means sharing the necessary resources, and thus a coordinated staggering of outages. In addition, nuclear fuel is an energy reserve which remains in the reactor for 3 or 4 years, with some of the fuel renewed each year. Due to the memory effect, the fuel retains a memory of past use, so that today's choices impact upon the future. A medium-term view of fuel management is also necessary. The coordination systems implemented by EDF aim to control these parameters for the benefit of electricity consumers. (author)

Nuclear generating station and heavy water plant cost estimates for strategy studies

International Nuclear Information System (INIS)

Archinoff, G.H.

1979-07-01

Nuclear generating station capital, operating and maintenance costs are basic input data for strategy analyses of alternate nuclear fuel cycles. This report presents estimates of these costs for natural uranium CANDU stations, CANDU stations operating on advanced fuel cycles, and liquid metal fast breeder reactors. Cost estimates for heavy water plants are also presented. The results show that station capital costs for advanced fuel cycles are not expected to be significantly greater than those for natural uranium stations. LMFBR capital costs are expected to be 25-30 percent greater than for CANDU's. (auth)

Evaluation of environmental data relating to selected nuclear power plant sites. Prairie Island Nuclear Generating Plant site

International Nuclear Information System (INIS)

Murarka, I.P.

1976-11-01

Environmental monitoring data for 1973 through 1975 pertaining to the Prairie Island Nuclear Generating Station (which began commercial operation in December 1973) were analyzed by the most practical qualitative and quantitative methods. Evaluations of aquatic and terrestrial biotic data are presented in this report. The data indicate no significant immediate deleterious effects on the biota from plant operation, thus confirming preoperational predictions. Although the station has not operated long enough to reveal long-term deleterious effects, present indications do not lead to a concerned prediction that any are developing. Recommendations are suggested for improving monitoring techniques

Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report

International Nuclear Information System (INIS)

Bond, L.G.; Doctor, S.R.; Gilbert, R.W.; Jarrell, D.B.; Greitzer, F.L.; Meador, R.J.

2000-01-01

OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities

Elecnuc - Nuclear power plants in the world - 2009 edition

International Nuclear Information System (INIS)

2009-01-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2008 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2008/01/01, Worldwide status of nuclear power plants (12/31/2008), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2008, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear powe plants by country at the end 2008, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2008, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2008, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2008, Long term shutdown units at 12/31/2008, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

ELECNUC Nuclear power plants in the world - 2013 edition

International Nuclear Information System (INIS)

2013-01-01

This small booklet summarizes in a series of tables the figures relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2012 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2012/01/01; Worldwide status of nuclear power plants (12/31/2012); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2012; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2012; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2012; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2012; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2012; Long term shutdown units at 12/31/2012; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

Impact of digital information and control system platform selection on nuclear power generating plant operating costs

International Nuclear Information System (INIS)

Bogard, T.; Radomski, S.; Sterdis, B.; Marta, H.; Bond, V.; Richardson, J.; Ramon, G.; Edvinsson, H.

1998-01-01

Information is presented on the benefits of a well-planned information and control systems (I and CS) replacement approach for aging nuclear power generating plants' I and CS. Replacement of an aging I and CS is accompanied by increases in plant profitability. Implementing a structured I and CS replacement with current technology allows improved plant electrical production in parallel with reduced I and CS operations and maintenance cost. Qualitative, quantitative, and enterprise management methods for cost benefit justification are shown to justify a comprehensive approach to I and CS replacement. In addition to the advantages of standard I and CS technologies, examples of new I and CS technologies are shown to add substantial cost benefit justification for I and CS replacements. Focus is upon I and CS replacements at nuclear power plants, however the information is applicable to other types of power generating facilities. (author)

Slovenske elektrarne, a.s., Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

1998-01-01

In this booklet the uranium atom nucleus fission as well as electricity generation in a nuclear power plant (primary circuit, reactor, reactor pressure vessel, fuel assembly, control rod and reactor power control) are explained. Scheme of electricity generation in nuclear power plant and Cross-section of Mochovce Nuclear Power Plant unit are included. In next part a reactor scram, refuelling of fuel, instrumentation and control system as well as principles of nuclear safety and safety improvements are are described

A Differential-Algebraic Model for the Once-Through Steam Generator of MHTGR-Based Multimodular Nuclear Plants

Directory of Open Access Journals (Sweden)

Zhe Dong

2015-01-01

Full Text Available Small modular reactors (SMRs are those fission reactors whose electrical output power is no more than 300 MWe. SMRs usually have the inherent safety feature that can be applicable to power plants of any desired power rating by applying the multimodular operation scheme. Due to its strong inherent safety feature, the modular high temperature gas-cooled reactor (MHTGR, which uses helium as coolant and graphite as moderator and structural material, is a typical SMR for building the next generation of nuclear plants (NGNPs. The once-through steam generator (OTSG is the basis of realizing the multimodular scheme, and modeling of the OTSG is meaningful to study the dynamic behavior of the multimodular plants and to design the operation and control strategy. In this paper, based upon the conservation laws of mass, energy, and momentum, a new differential-algebraic model for the OTSGs of the MHTGR-based multimodular nuclear plants is given. This newly-built model can describe the dynamic behavior of the OTSG in both the cases of providing superheated steam and generating saturated steam. Numerical simulation results show the feasibility and satisfactory performance of this model. Moreover, this model has been applied to develop the real-time simulation software for the operation and regulation features of the world first underconstructed MHTGR-based commercial nuclear plant—HTR-PM.

Research and engineering application of coordinated instrumentation control and protection technology between reactor and steam turbine generator on nuclear power plant

International Nuclear Information System (INIS)

Sun Xingdong

2014-01-01

The coordinated instrumentation control and protection technology between reactor and steam turbine generator (TG) usually is very significant and complicated for a new construction of nuclear power plant, because it carries the safety, economy and availability of nuclear power plant. Based on successful practice of a nuclear power plant, the experience on interface design and hardware architecture of coordinated instrumentation control and protection technology between reactor and steam turbine generator was abstracted and researched. In this paper, the key points and engineering experience were introduced to give the helpful instructions for the new project. (author)

Economics of generating electricity from nuclear power

International Nuclear Information System (INIS)

Boadu, H.O.

2001-01-01

The paper reviews and compares experiences and projected future construction and electricity generation costs for nuclear and fossil fired power plants. On the basis of actual operating experience, nuclear power has been demonstrated to be economically competitive with other base load generation options, and international studies project that this economic competitiveness will be largely maintained in the future, over a range of conditions and in a number of countries. However, retaining and improving this competitive position requires concerted efforts to ensure that nuclear plants are constructed within schedule and budgets, and are operated reliably and efficiently. Relevant cost impacting factors is identified, and conclusions for successful nuclear power plant construction and operation are drawn. The desire to attain sustainable development with balanced resource use and control of the environmental and climate impacts of energy systems could lead to renewed interest in nuclear power as an energy source that does not emit greenhouse gases, thus contributing to a revival of the nuclear option. In this regard, mitigation of emissions from fossil-fuelled power plants could lead to restrictions of fossil fuel use and/or result in higher costs of fossil based generation, thus improving the economic competitiveness of nuclear power (au)

Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report

Energy Technology Data Exchange (ETDEWEB)

L. J. Bond; S. R. Doctor; R. W. Gilbert; D. B. Jarrell; F. L. Greitzer; R. J. Meador

2000-09-01

OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities.

Control-oriented modeling of the energy-production of a synchronous generator in a nuclear power plant

International Nuclear Information System (INIS)

Fodor, Attila; Magyar, Attila; Hangos, Katalin M.

2012-01-01

Nuclear Power Plant (Hungary) is developed in this paper based on first engineering principles that is able to describe the time-varying active and reactive power output of the generator. These generators are required to take part in the reactive power support of the power grid following the demand of a central dispatch center, and also contribute to the frequency control of the grid. The developed model has been verified under the usual controlled operating conditions when the frequency and the active power are controlled. Static and dynamic sensitivity analysis has been applied to determine the model parameters to be estimated. The model parameters have been estimated applying the asynchronous parallel pattern search method using real measured data from the nuclear power plant. The confidence regions in the parameter space have been analyzed by investigating the geometry of the estimation error function. The developed model can serve as a basis for controlling the optimal energy production of the generator using both the active and reactive power components. -- Highlights: ► A dynamic model of a synchronous generator in a Nuclear Power Plant is developed. ► The model has been verified under the usual controlled operating conditions. ► The sensitivity analysis has been applied to determine the model parameters. ► The parameters have been estimated applying the APPS method using measured data. ► The model serves as a basis for controlling the optimal energy production of the generator.

Operating experience with diesel generators in Belgian nuclear power plants

International Nuclear Information System (INIS)

Merny, R.

1986-01-01

Various problems have occurred on the diesel generators in the Belgian nuclear power plants, independently of the D.G. manufacturer or from the operating crew. Furthermore no individual part of the D.G. can be incriminated as being the main cause of the incidents. The incidents reported in this paper are chosen because of the importance for the safety or for the long repair period. The unavailability of a D.G. can only be detected by periodic tests and controls. Combined with a good preventive maintenance, the risks of incidents can be reduced. (author)

Operating experience with diesel generators in Belgian nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Merny, R. [Association Vincotte, Avenue du Roi 157, B-1060 Bruxelles/Brussels (Belgium)

1986-02-15

Various problems have occurred on the diesel generators in the Belgian nuclear power plants, independently of the D.G. manufacturer or from the operating crew. Furthermore no individual part of the D.G. can be incriminated as being the main cause of the incidents. The incidents reported in this paper are chosen because of the importance for the safety or for the long repair period. The unavailability of a D.G. can only be detected by periodic tests and controls. Combined with a good preventive maintenance, the risks of incidents can be reduced. (author)

Optimal sampling period of the digital control system for the nuclear power plant steam generator water level control

International Nuclear Information System (INIS)

Hur, Woo Sung; Seong, Poong Hyun

1995-01-01

A great effort has been made to improve the nuclear plant control system by use of digital technologies and a long term schedule for the control system upgrade has been prepared with an aim to implementation in the next generation nuclear plants. In case of digital control system, it is important to decide the sampling period for analysis and design of the system, because the performance and the stability of a digital control system depend on the value of the sampling period of the digital control system. There is, however, currently no systematic method used universally for determining the sampling period of the digital control system. Generally, a traditional way to select the sampling frequency is to use 20 to 30 times the bandwidth of the analog control system which has the same system configuration and parameters as the digital one. In this paper, a new method to select the sampling period is suggested which takes into account of the performance as well as the stability of the digital control system. By use of the Irving's model steam generator, the optimal sampling period of an assumptive digital control system for steam generator level control is estimated and is actually verified in the digital control simulation system for Kori-2 nuclear power plant steam generator level control. Consequently, we conclude the optimal sampling period of the digital control system for Kori-2 nuclear power plant steam generator level control is 1 second for all power ranges. 7 figs., 3 tabs., 8 refs. (Author)

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).

Generation IV nuclear plant design strategies

International Nuclear Information System (INIS)

Altin, V.

2007-01-01

In this presentation Generation IV nuclear reactor design criteria are examined under the light of known nuclear properties of fissile and fertile nuclei. Their conflicting nature is elucidated along with the resulting inevitability of a multitude of designs. The designs selected as candidates for further development are evaluated with respect to their potential to serve the different design criteria, thereby revealing their more difficult aspects of realization and the strong research challenges lying ahead

Consolidated nuclear steam generator

International Nuclear Information System (INIS)

Jabsen, F.S.; Schluderberg, D.C.; Paulson, A.E.

1978-01-01

An improved system of providing power has a unique generating means for nuclear reactors with a number of steam generators in the form of replaceable modular units of the expendable type to attain the optimum in effective and efficient vaporization of fluid during the generating power. The system is most adaptable to undrground power plants and marine usage

Slovak Electric, plc, Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

1999-01-01

In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

Next Generation Nuclear Plant Materials Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-09-01

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

Chemical Plant Accidents in a Nuclear Hydrogen Generation Scheme

International Nuclear Information System (INIS)

Brown, Nicholas R.; Revankar, Shripad T.

2011-01-01

A high temperature nuclear reactor (HTR) could be used to drive a steam reformation plant, a coal gasification facility, an electrolysis plant, or a thermochemical hydrogen production cycle. Most thermochemical cycles are purely thermodynamic, and thus achieve high thermodynamic efficiency. HTRs produce large amounts of heat at high temperature (1100 K). Helium-cooled HTRs have many passive, or inherent, safety characteristics. This inherent safety is due to the high design basis limit of the maximum fuel temperature. Due to the severity of a potential release, containment of fission products is the single most important safety issue in any nuclear reactor facility. A HTR coupled to a chemical plant presents a complex system, due primarily to the interactive nature of both plants. Since the chemical plant acts as the heat sink for the nuclear reactor, it important to understand the interaction and feedback between the two systems. Process heat plants and HTRs are generally very different. Some of the major differences include: time constants of plants, safety standards, failure probability, and transient response. While both the chemical plant and the HTR are at advanced stages of testing individually, no serious effort has been made to understand the operation of the integrated system, especially during accident events that are initiated in the chemical plant. There is a significant lack of knowledge base regarding scaling and system integration for large scale process heat plants coupled to HTRs. Consideration of feedback between the two plants during time-dependent scenarios is absent from literature. Additionally, no conceptual studies of the accidents that could occur in either plant and impact the entire coupled system are present in literature

Water releasing electric generating device for nuclear power plant

International Nuclear Information System (INIS)

Umehara, Toshihiro; Tomohara, Yasutaka; Usui, Yoshihiko.

1994-01-01

Warm sea water discharged after being used for cooling in an equipment of a coastal nuclear powder plant is discharged from a water discharge port to a water discharge pit, and a conduit vessel is disposed in front of the water discharge port for receiving overflown warm sea water. The warm sea water taken to the conduit vessel is converted to a fallen flow and charged to a turbine generator under water, and electric power is generated by the water head energy of the fallen flow before it is discharged to the water discharge pit. The conduit vessel incorporates a foam preventing unit having spiral flow channels therein, so that the warm sea water taken to the conduit vessel is flown into the water discharge pit after consuming the water head energy while partially branched and flown downwardly and gives lateral component to the downwarding flowing direction. Then, warm sea water is made calm when it is flown into the water discharge pit and, accordingly, generation of bubbles on the water surface of the water discharge pit is avoided. (N.H.)

Possibilities of the metallurgical base in the manufacture of tubes for nuclear power plant steam generators

International Nuclear Information System (INIS)

Prnka, T.; Walder, V.; Dolenek, J.

Current possibilities are briefly summarized of metallurgy in the manufacture of high-quality tubes for nuclear power plant steam generators, mainly for fast reactor power plants. Discussed are steel making possibilities, semi-finished product and tube forming with special regard to 2.25Cr1MoNiNb steel problems, heat treatment, finishing, and testing. Necessary equipment and technology for the production of steam generator tubes are less common in the existing practice and are demanding on investment; their introduction, however, is inevitable for securing quality production of steam generator tubes. (Kr)

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)

Next Generation Nuclear Plant Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

None

2005-01-01

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

Risk of nuclear power generation as business (continued)

International Nuclear Information System (INIS)

Sato, Satoshi

2017-01-01

This paper described the following: (1) fleet formation of power companies that operate nuclear power plants in the U.S., (2) collaboration, competition, and merger between plant makers, (3) stress corrosion cracking of stream generators for PWR and their thin heat transfer tubes, especially stress corrosion cracking under primary cooling water environment (PWSCC), and (4) replacement project from Inconel 600 MA to Inconel 600 TT or 690 TT of steam generator thin heat transfer tubes of PWR plants in the U.S. and others. In addition, it described the troubles at San Onofre Nuclear Power Station in California: wear of steam generator thin tubes of Units 2 and 3, and leakage from primary system to secondary system of Unit 3, and permanent shutdown. It also described the detail of damages compensation talks between South California Edison Company that operates San Onofre nuclear power plant and Mitsubishi Heavy Industries Ltd. which supplied the steam generator. Although the operation of the 1.7 million kW plant became impossible due to the bud shedding of nuclear power renaissance, these troubles might have saved the nightmare of drifting on the way. (A.O.)

Modular steam generator for use in nuclear power plants

International Nuclear Information System (INIS)

Cella, A.

1979-01-01

An improved steam generator for a PWR is described. A turbine generator is driven by the steam output of the steam generator to provide electrical power. The improvement provides vertically assemblable modules which are removably mounted together in sealing relationship. The modules comprising a base module, a tube bundle module removably mountable on the base module in sealing relationship, and an uppermost dryer module removably mountable on the tube bundle module in sealing relationship. Ready access to and removal of the tube bundle module in situ from the nuclear power plant steam generator is facilitated. The dryer module contains moisture separator for drying the generated steam. The base module, upon which the associated weight of the vertically assembled dryer module and tube bundle module are supported, contains the inlet and outlet for the heat exchange fluid. The tube bundle module contains the tube bundle through which the heat exchange fluid flows as well as an inlet for feedwater. The tube sheet serves as a closure flange for the tube bundle module, with the associated weight of the vertically assembled dryer module and tube bundle module on the tube sheet closure flange effectuating the sealing relationship between the base module and the tube bundle module for facilitating closure

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

Energy Technology Data Exchange (ETDEWEB)

G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

2007-09-01

DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

Next Generation Nuclear Plant Intermediate Heat Exchanger Acquisition Strategy

Energy Technology Data Exchange (ETDEWEB)

Mizia, Ronald Eugene [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2008-04-01

DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C to 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium cooled, prismatic or pebble-bed reactor, and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. The purpose of this report is to address the acquisition strategy for the NGNP Intermediate Heat Exchanger (IHX).This component will be operated in flowing, impure helium on the primary and secondary side at temperatures up to 950°C. There are major high temperature design, materials availability, and fabrication issues that need to be addressed. The prospective materials are Alloys 617, 230, 800H and X, with Alloy 617 being the leading candidate for the use at 950°C. The material delivery schedule for these materials does not pose a problem for a 2018 start up as the vendors can quote reasonable delivery times at the moment. The product forms and amount needed must be finalized as soon as possible. An

Performance of Generating Plant: Managing the Changes. Part 2: Thermal Generating Plant Unavailability Factors and Availability Statistics

Energy Technology Data Exchange (ETDEWEB)

Curley, G. Michael [North American Electric Reliability Corporation (United States); Mandula, Jiri [International Atomic Energy Agency (IAEA)

2008-05-15

The WEC Committee on the Performance of Generating Plant (PGP) has been collecting and analysing power plant performance statistics worldwide for more than 30 years and has produced regular reports, which include examples of advanced techniques and methods for improving power plant performance through benchmarking. A series of reports from the various working groups was issued in 2008. This reference presents the results of Working Group 2 (WG2). WG2's main task is to facilitate the collection and input on an annual basis of power plant performance data (unit-by-unit and aggregated data) into the WEC PGP database. The statistics will be collected for steam, nuclear, gas turbine and combined cycle, hydro and pump storage plant. WG2 will also oversee the ongoing development of the availability statistics database, including the contents, the required software, security issues and other important information. The report is divided into two sections: Thermal generating, combined cycle/co-generation, combustion turbine, hydro and pumped storage unavailability factors and availability statistics; and nuclear power generating units.

Dynamic modelling of nuclear steam generators

International Nuclear Information System (INIS)

Kerlin, T.W.; Katz, E.M.; Freels, J.; Thakkar, J.

1980-01-01

Moving boundary, nodal models with dynamic energy balances, dynamic mass balances, quasi-static momentum balances, and an equivalent single channel approach have been developed for steam generators used in nuclear power plants. The model for the U-tube recirculation type steam generator is described and comparisons are made of responses from models of different complexity; non-linear versus linear, high-order versus low order, detailed modeling of the control system versus a simple control assumption. The results of dynamic tests on nuclear power systems show that when this steam generator model is included in a system simulation there is good agreement with actual plant performance. (author)

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

International Nuclear Information System (INIS)

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

1981-01-01

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

Small Nuclear Co-generation Plants Based on Shipbuilding Technology

International Nuclear Information System (INIS)

Vasyukov, V. I.; Veshnyakov, K. B.; Goryunov, E. V.; Zalugin, V. I.; Panov, Yu. K.; Polunichev, V. I.

2002-01-01

The development of nuclear cogeneration plants and power desalination complexes of relatively small power, using proven shipbuilding technology, becomes more and more attractive for solving the power supply problems of remote districts of the Extreme North and the Far East with small and medium power grids and for removing the shortage of fresh water in different world regions. The idea of transportation of the power unit with high degree of readiness to the place of its location with minimum construction and mounting activities at the site is very attractive. Compactness typical of RP based on shipbuilding technology allows to develop floating or ground-based plants at minimum use of water area and territory. Small construction scope at the site under conditions of minimum anthropogenic loads and high ecological indices are important arguments in favor of floating nuclear cogeneration plant based on ship power units against the alternative fossil sources. At present, the activities on floating nuclear cogeneration plant design, which is developed on the basis of floating power unit with two KLT-40S reactor plant, which is a modified option of standard KLT-40-type ship plant for icebreaker fleet in Russia are the most advanced. To date, a detailed design of reactor plant has been developed and approved, design activities on floating power unit are in the stage of completion, the site for its location has been selected and licensing by GAN, Russia, is in progress. Besides OKBM has developed some designs of nuclear cogeneration plants of different power on the basis of integral reactor plants, using the experience of transport and stationary power plants designing. Nuclear cogeneration plant investment analysis showed acceptable social and economical efficiency of the design that creates conditions for commercial construction of floating power units with KLT-40S reactor plan. At the same time the reduction of the design recovering terms, increase of budget income and

SWOT of nuclear power plant sustainable development

International Nuclear Information System (INIS)

Abbaspour, M.; Ghazi, S.

2008-01-01

SWOT Analysis is a Useful tool that can he applied to most projects or business ventures. In this article we are going to examine major strengths, weaknesses, opportunities and threats of nuclear power plants in view of sustainable development. Nuclear power plants have already attained widespread recognition for its benefits in fossil pollution abatement, near-zero green house gas emission, price stability and security of energy supply. The impressive new development is that these virtues are now a cost -free bonus, because, in long run, nuclear energy has become an inexpensive way to generate electricity. Nuclear energy's pre-eminence economically and environmentally has two implications for government policy. First, governments should ensure that nuclear licensing and safety oversight arc not only rigorous but also efficient in facilitating timely development of advanced power plants. Second, governments should be bold incentivizing the transformation to clean energy economics, recognizing that such short-term stimulus will, in the case of nuclear plants, simply accelerate desirable changes that now have their own long-term momentum. The increased competitiveness of nuclear power plant is the result of cost reductions in all aspects of nuclear economics: Construction, financing, operations, waste management and decommissioning. Among the cost-lowering factors are the evolution to standardized reactor designs, shorter construction periods, new financing techniques, more efficient generation technologies, higher rates of reactor utilization, and longer plant lifetimes. U.S World Nuclear Association report shows that total electricity costs for power plant construction and operation were calculated at two interest rates. At 10%, midrange generating costs per kilowatt-hour are nuclear at 4 cents, coal at 4.7 cents and natural gas at 5.1 cent. At a 5% interest rate, mid-range costs per KWh fall to nuclear at 2.6 cents, coal at 3.7 cents and natural gas at 4.3 cents

Nuclear performance standards: Promoting efficient generation

International Nuclear Information System (INIS)

Nagelhout, M.

1990-01-01

Nuclear plant performance standards are designed to share the risks of operation associated with nuclear generation. Such standards often shift risks from ratepayers to utility shareholders, even without a finding of imprudence or mismanagement. The rationale underlying nuclear performance standards is that ratepayers should not be responsible for excessive replacement power costs incurred as a result of unreasonable decisions by utility management, especially because the high fixed costs of nuclear plants are already included in base rates. In addition, performance standards can be designed to provide incentives to reward utilities that achieve superior nuclear performance, for the benefit of both ratepayers and shareholders

Nuclear power generation and fuel cycle report 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

Nuclear power generation and fuel cycle report 1996

International Nuclear Information System (INIS)

1996-10-01

This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included

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.)

Next Generation Nuclear Plant Materials Research and Development Program Plan

International Nuclear Information System (INIS)

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-01-01

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R and D) Program is responsible for performing R and D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R and D Program includes the following elements: (1) Developing a specific approach, program plan and other project management

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

International Nuclear Information System (INIS)

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

1975-01-01

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

Potential of light water reactors for future nuclear power plants

International Nuclear Information System (INIS)

Gueldner, R.

2003-01-01

Energy consumption worldwide is going to increase further in the next few decades. Reliable supplies of electricity can be achieved only by centralized power plant structures. In this scenario, nuclear power plants are going to play a leading role as reliable and competitive plants, also under deregulated market conditions. Today, light water reactors have achieved a leading position, both technically and economically, contributing 85% to worldwide electricity generation in nuclear plants. They will continue to be a proven technology in power generation. In many countries, activities therefore are concentrated on extending the service life of plants beyond a period of forty years. New nuclear generating capacities are expected to be created and added from the end of this decade onward. Most of this capacity will be in light water reactors. The concepts of third-generation reactors will meet all economic and technical safety requirements of the 21st century and will offer considerable potential for further development. Probably some thirty years from now, fourth-generation nuclear power plants will be ready for commercial application. These plants will penetrate especially new sectors of the energy markets. Public acceptance of new nuclear power plants is not a matter of reactor lines, provided that safety requirements are met. The important issue is the management of radioactive waste. The construction of new nuclear power plants in Western Europe and North America mainly hinges on the ability to explain to the public that there is a need for new plants and that nuclear power is fundamental to assuring sustainable development. (orig.)

New generation nuclear power units of PWR type integral reactors

International Nuclear Information System (INIS)

Mitenkov, F.M.; Kurachen Kov, A.V.; Malamud, V.A.; Panov, Yu.K.; Runov, B.I.; Flerov, L.N.

1997-01-01

Design bases of new generation nuclear power units (nuclear power plants - NPP, nuclear co-generation plants - NCP, nuclear distract heating plants - NDHP), using integral type PWPS, developed in OKBM, Nizhny Novgorod and trends of design decisions optimization are considered in this report. The problems of diagnostics, servicing and repair of the integral reactor components in course of operation are discussed. The results of safety analysis, including the problems of several accident localization with postulated core melting and keeping corium in the reactor vessel and guard vessel are presented. Information on experimental substantiation of the suggested plant design decisions is presented. (author)

Hydrogen Generation, Combustibility and Mitigation in Nuclear Power Plant Systems

International Nuclear Information System (INIS)

Talha, K.A.; El-Sheikh, B.M.; Gad El-Mawla, A.S.

2003-01-01

The nuclear power plant is provided with features to insure safety. The engineered safety features (ESFs) are devoted to set operating conditions under accident conditions. If ESFs fail to apply in some accidents, this would lead to what called severe accidents, and core damage. In this case hydrogen will be generated from different sources particularly from metal-water reactions. Since the containment is the final barrier to protect the environment from the release of radioactive materials; its integrity should not be threatened. In recent years, hydrogen concentration represents a real problem if it exceeds the combustibility limits. This work is devoted to calculate the amount of hydrogen to be generated, indelicate its combustibility and how to inertize the containment using different gases to maintain its integrity and protect the environment from the release of radioactive materials

Present status and problems of nuclear power generation

International Nuclear Information System (INIS)

Harada, Hiroshi.

1984-01-01

The nuclear power generation in Japan began in 1963 with the successful power generation in the JPDR of the Japan Atomic Energy Research Institute, and since then, more than 20 years have elapsed. The Japan Atomic Power Co. started the operation of an imported Calder Hall type gas-cooled reactor with 166,000 kWe output in Tokai Nuclear Power Station in July, 1966. In 1983, the quantity of nuclear power generation was 113.1 billion kWh, which was equivalent to 21.4 % of the total power generation in Japan. As of April 1, 1984, 25 nuclear power plants with 18.28 million kW output were in operation, 12 plants of 11.8 million kW were under construction, and 7 plants of 6.05 million kW were in preparation phase. Besides, the ATR ''Fugen'' with 165,000 kW output has been in operation, and the FBR ''Monju'' with 280,000 kW output is under construction. The capacity ratio of Japanese nuclear power stations attained 71.5 % in 1983. According to the ''Long term energy demand and supply outlook'' revised in November, 1983, the nuclear power generation in 2000 will be about 62 million kW to cater for about 16 % of primary energy supply. The problems are the improvement of economy, the establishment of independent nuclear fuel cycle, the decommissioning of nuclear reactors and so on. (Kako, I.)

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

International Nuclear Information System (INIS)

De Greef, J.F.

1985-01-01

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

Modelling of nuclear power plant decommissioning financing.

Science.gov (United States)

Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

2015-06-01

Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Some environmental effects of emissions from CANDU nuclear generating stations and heavy water plants

International Nuclear Information System (INIS)

Effer, W.R.

Non-radioactive releases during normal operation of Ontario Hydro's nuclear generating stations and heavy water plants are summarized and related to existing regulations and guidelines. Low-grade heat in the circulating cooling water discharge is the most important of the non-radioactive effluents. Some of the hydrological, biological and water quality aspects of thermal discharges are discussed in relation to the operation of Ontario Hydro's thermal generating stations on the Great Lakes. Chemical releases to air or water include chlorine, hydrogen sulphide, water treatment plant effluents, oily waste water and sewage lagoon effluents. The significance of the first two of these releases to the environment is reviewed, particularly in relation to Great Lakes water quality and biological concerns. (author)

A Systems Engineering Framework for Design, Construction and Operation of the Next Generation Nuclear Plant

International Nuclear Information System (INIS)

Edward J. Gorski; Charles V. Park; Finis H. Southworth

2004-01-01

Not since the International Space Station has a project of such wide participation been proposed for the United States. Ten countries, the European Union, universities, Department of Energy (DOE) laboratories, and industry will participate in the research and development, design, construction and/or operation of the fourth generation of nuclear power plants with a demonstration reactor to be built at a DOE site and operational by the middle of the next decade. This reactor will be like no other. The Next Generation Nuclear Plant (NGNP) will be passively safe, economical, highly efficient, modular, proliferation resistant, and sustainable. In addition to electrical generation, the NGNP will demonstrate efficient and cost effective generation of hydrogen to support the President's Hydrogen Initiative. To effectively manage this multi-organizational and technologically complex project, systems engineering techniques and processes will be used extensively to ensure delivery of the final product. The technological and organizational challenges are complex. Research and development activities are required, material standards require development, hydrogen production, storage and infrastructure requirements are not well developed, and the Nuclear Regulatory Commission may further define risk-informed/performance-based approach to licensing. Detailed design and development will be challenged by the vast cultural and institutional differences across the participants. Systems engineering processes must bring the technological and organizational complexity together to ensure successful product delivery. This paper will define the framework for application of systems engineering to this $1.5B - $1.9B project

Nuclear power plants: 2013 atw compact statistics

Energy Technology Data Exchange (ETDEWEB)

Anon.

2014-03-15

At the end of 2013, nuclear power plants were available for energy supply in 31 countries of the world. A total of 437 nuclear power plants were in operation with an aggregate gross power of approx. 393 GWe and an aggregate net power, respectively, of 372 GWe. This means that the number was unchanged compared to the previous year's number on 31 December 2012. The available gross power of nuclear power plants increased by approx. 2 GWe from 2012 to the end of 2013. In total 4 nuclear generating units were commissioned in 2013 in China (+2) and in the Republic Korea (+1). 6 nuclear generating units were decommissioned in 2013. Four units in the U.S.A. (-4) were shut down due to economical reasons. In Canada (-2) the operation status of 2 units was changed from long-term shutdown to permanently shutdown. 70 nuclear generating units with an aggregate gross power of approx. 73 GWe, were under construction in 15 countries end of 2013. New or continued projects are notified from (in brackets: number of new projects) China (+3), Belarus (+1), Rep. of Korea (+1) and the United Arab Emirates (+1). Some 115 new nuclear power plants are in the concrete project design, planning and licensing phases worldwide; on some of them, contracts have already been awarded. Another units are in their preliminary project phases. (orig.)

Nuclear power plants: 2013 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2014-01-01

At the end of 2013, nuclear power plants were available for energy supply in 31 countries of the world. A total of 437 nuclear power plants were in operation with an aggregate gross power of approx. 393 GWe and an aggregate net power, respectively, of 372 GWe. This means that the number was unchanged compared to the previous year's number on 31 December 2012. The available gross power of nuclear power plants increased by approx. 2 GWe from 2012 to the end of 2013. In total 4 nuclear generating units were commissioned in 2013 in China (+2) and in the Republic Korea (+1). 6 nuclear generating units were decommissioned in 2013. Four units in the U.S.A. (-4) were shut down due to economical reasons. In Canada (-2) the operation status of 2 units was changed from long-term shutdown to permanently shutdown. 70 nuclear generating units with an aggregate gross power of approx. 73 GWe, were under construction in 15 countries end of 2013. New or continued projects are notified from (in brackets: number of new projects) China (+3), Belarus (+1), Rep. of Korea (+1) and the United Arab Emirates (+1). Some 115 new nuclear power plants are in the concrete project design, planning and licensing phases worldwide; on some of them, contracts have already been awarded. Another units are in their preliminary project phases. (orig.)

Hydrogen generation comparison between lead-calcium and lead-antimony batteries in nuclear power plant

International Nuclear Information System (INIS)

Zhao Hongjun; Qi Suoni; Shen Yan; Li Jia

2014-01-01

Battery type selection is performed with the help of technical information supplied by vendors, and according to relevant criteria. Analysis and comparison of the hydrogen generation differences between two different lead-acid battery types are carried out through calculation. The analysis result may provide suggestions for battery type selection in nuclear power plant. (authors)

Reactor type choice and characteristics for a small nuclear heat and electricity co-generation plant

International Nuclear Information System (INIS)

Liu Kukui; Li Manchang; Tang Chuanbao

1997-01-01

In China heat supply consumes more than 70 percent of the primary energy resource, which makes for heavy traffic and transportation and produces a lot of polluting materials such as NO x , SO x and CO 2 because of use of the fossil fuel. The utilization of nuclear power into the heat and electricity co-generation plant contributes to the global environmental protection. The basic concept of the nuclear system is an integral type reactor with three circuits. The primary circuit equipment is enclosed in and linked up directly with reactor vessel. The third circuit produces steam for heat and electricity supply. This paper presents basic requirements, reactor type choice, design characteristics, economy for a nuclear co-generation plant and its future application. The choice of the main parameters and the main technological process is the key problem of the nuclear plant design. To make this paper clearer, take for example a double-reactor plant of 450 x 2MW thermal power. There are two sorts of main technological processes. One is a water-water-steam process. Another is water-steam-steam process. Compared the two sorts, the design which adopted the water-water-steam technological process has much more advantage. The system is simplified, the operation reliability is increased, the primary pressure reduces a lot, the temperature difference between the secondary and the third circuits becomes larger, so the size and capacity of the main components will be smaller, the scale and the cost of the building will be cut down. In this design, the secondary circuit pressure is the highest among that of the three circuits. So the primary circuit radioactivity can not leak into the third circuit in case of accidents. (author)

Financial analysis of large versus small nuclear power plants

International Nuclear Information System (INIS)

Louh, R.F.; Becker, M.; Wicks, F.

1986-01-01

There have been no new orders for nuclear plants and many nuclear plants under construction have been cancelled in recent years in the United States. Financing problems have been a major factor in this slow down of new nuclear plant activity. Meanwhile, the nuclear plants that have been completed have been operating cost effectively and yielding fossil fuel conservation and air quality benefits. Smaller plants have been designed in the past for the purpose of penetrating markets in developing countries and countries with relatively small utility systems. This paper examines the question of whether these smaller plants would be a viable option to large nuclear plants in the United States. Although the smaller plants are estimated to have a somewhat higher capital cost on a $/k W basis, they have the potential advantage of a lower total financial committment. The computational tools required for this evaluation are optimal generation planning and financial simulation programs and the corresponding generation and financial data bases for a variety of systems

Medium-size nuclear plants

International Nuclear Information System (INIS)

Vogelweith, L.; Lavergne, J.C.; Martinot, G.; Weiss, A.

1977-01-01

CEA (TECHNICATOME) has developed a range of pressurized water reactors of the type ''CAS compact'' which are adapted to civil ship propulsion, or to electric power production, combined possibly with heat production, up to outputs equivalent to 125 MWe. Nuclear plants equipped with these reactors are suitable to medium-size electric networks. Among the possible realizations, two types of plants are mentioned as examples: 1) Floating electron-nuclear plants; and 2) Combined electric power and desalting plants. The report describes the design characteristics of the different parts of a 125 MWe unit floating electro-nuclear plant: nuclear steam system CAS 3 G, power generating plant, floating platform for the whole plant. The report gives attention to the different possibilities according to site conditions (the plant can be kept floating, in a natural or artificial basin, it can be put aground, ...) and to safety and environment factors. Such unit can be used in places where there is a growing demand in electric power and fresh water. The report describes how the reactor, the power generating plant and multiflash distillation units of an electric power-desalting plant can be combined: choice of the ratio water output/electric power output, thermal cycle combination, choice of the gain ratio, according to economic considerations, and to desired goal of water output. The report analyses also some technical options, such as: choice of the extraction point of steam used as heat supply of the desalting station (bleeding a condensation turbine, or recovering steam at the exhaust of a backpressure turbine), design making the system safe. Lastly, economic considerations are dealt with: combining the production of fresh water and electric power provides usually a much better energy balance and a lower cost for both products. Examples are given of some types of installations which combine medium-size reactors with fresh water stations yielding from 10000 to 120000 m 3 per day

Nuclear power generation and nuclear fuel

International Nuclear Information System (INIS)

Okajima, Yasujiro

1985-01-01

As of June 30, 1984, in 25 countries, 311 nuclear power plants of about 209 million kW were in operation. In Japan, 27 plants of about 19 million kW were in operation, and Japan ranks fourth in the world. The present state of nuclear power generation and nuclear fuel cycle is explained. The total uranium resources in the free world which can be mined at the cost below $130/kgU are about 3.67 million t, and it was estimated that the demand up to about 2015 would be able to be met. But it is considered also that the demand and supply of uranium in the world may become tight at the end of 1980s. The supply of uranium to Japan is ensured up to about 1995, and the yearly supply of 3000 st U 3 O 8 is expected in the latter half of 1990s. The refining, conversion and enrichment of uranium are described. In Japan, a pilot enrichment plant consisting of 7000 centrifuges has the capacity of about 50 t SWU/year. UO 2 fuel assemblies for LWRs, the working of Zircaloy, the fabrication of fuel assemblies, the quality assurance of nuclear fuel, the behavior of UO 2 fuel, the grading-up of LWRs and nuclear fuel, and the nuclear fuel business in Japan are reported. The reprocessing of spent fuel and plutonium fuel are described. (Kako, I.)

Trend in foreign countries of life extension for nuclear power plants

International Nuclear Information System (INIS)

Kusanagi, Hideo

1992-01-01

When the nuclear power generation in the world is converted to oil burning thermal power generation, the required quantity of oil is twice as much as the oil production in Saudi Arabia. This represents the size of the role that nuclear power generation plays. More than 30 years have already elapsed since the start of nuclear power generation, and the number of nuclear power plants in operation in the world was 426 as of the end of 1990, and their capacity of about 344 million kW is about 17% of the total generated electric power in the world. Though circumstances are different in respective countries, the construction of new nuclear power plants is not always advancing smoothly, and the possibility of operating existing nuclear power plants as long as possible has been investigated. In USA, the approved term of operation of nuclear power plants is 40 years, and the trend of the research and development of the plant life extension is described. In France, the life of nuclear power plants is not stipulated by the law. In U.K., also it is not stipulated by the law. The trend in these countries is reported. IAEA also has carried out the activities on this problem. (K.I.)

Development of technology for next generation reactor - Research of evaluation technology for nuclear power plant -

Energy Technology Data Exchange (ETDEWEB)

Park, Jong Kyun; Chang, Moon Heuy; Hwang, Yung Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)] [and others

1993-09-01

For development of next generation reactor, a project for evaluation technology for nuclear power plant is performed. Evaluation technology is essential to next generation reactor for reactor safety and system analysis. For design concept, detailed evaluation technologies are studied as follows: evaluation of safety margin, evaluation of safety facilities, evaluation of measurement and control technology; man-machine interface. Especially for thermal efficiency, thermal properties and chemical composition of inconel 690 tube, instead of inconel 600 tube, are measured for steam generator. (Author).

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

Next Generation Nuclear Plant Methods Technical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Metrology for New Generation Nuclear Power Plants - MetroFission

International Nuclear Information System (INIS)

Johansson, Lena; Dinsdale, Alan; Keightley, John; Filtz, Jean-Remy; Hay, Bruno; DeFelice, Pierino; Sadli, Mohamed; Plompen, Arjan; Heyse, Jan; Pomme, Stefaan; Cassette, Philippe

2013-06-01

MetroFission project has been looking at solving metrological problems related to a new generation of NPPs. The proposed Gen. IV NPPs are designed to run safely, make efficient use of natural resources, minimize the waste and maintain proliferation resistance. In order to reach these goals, the reactor operation involves higher temperatures, high-energy neutron fluence, different types of fuel where the minor actinides are included etc. The work has focused on improved temperature measurements, investigation of thermal properties of advanced materials, determination of new and relevant nuclear data and development of measurement techniques for radionuclides suitable for Gen. IV NPPs. The improved temperature measurement for nuclear power plant applications includes the development of a new Fe-C fixed point. Robust, repeatable and versatile cells have been constructed and compared with success among the project participants and their melting temperatures have been determined. Methodology of self-validating thermocouples has proven efficient at several fixed point temperatures using different designs. A practical acoustic thermometer has been tested at 1000 deg. C with success thanks to the use of innovative signal processing methods. Mo/Nb thermocouples have been obtained with different sheath materials and tested with the aim to achieve for the first time a reference function determined with the best possible uncertainties. Following reviews of designs and technology proposed for fourth generation nuclear plants effort within this project, with regards to thermal properties of advanced materials for nuclear design, has concentrated on provision of thermodynamic data to support the development of the sodium cooled fast reactor. Data has been critically assessed to represent the potential interaction between the Na coolant and the nuclear fuel taken to be based on (U, Pu)O 2 but incorporating minor actinides such as Np and Am. Data for the fission products and

Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

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.)

An integral reactor design concept for a nuclear co-generation plant

International Nuclear Information System (INIS)

Lee, D.J.; Kim, J.I.; Kim, K.K.; Chang, M.H.; Moon, K.S.

1997-01-01

An integral reactor concept for nuclear cogeneration plant is being developed at KAERI as an attempt to expand the peaceful utilization of well established commercial nuclear technology, and related industrial infrastructure such as desalination technology in Korea. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway to evaluate the characteristics of various passive safety concepts and provide the proper technical data for the conceptual design. This paper describes the preliminary safety and design concepts of the advanced integral reactor. Salient features of the design are hexagonal core geometry, once-through helical steam generator, self-pressurizer, and seismic resistant fine control CEDMS, passive residual heat removal system, steam injector driven passive containment cooling system. (author)

Nuclear power plant status diagnostics using artificial neural networks

International Nuclear Information System (INIS)

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

1991-01-01

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

Survey of insulation used in nuclear power plants and the potential for debris generation

International Nuclear Information System (INIS)

Kolbe, R.; Gahan, E.

1982-05-01

In support of Unresolved Safety Issue, USI A-43, Containment emergency Sump Performance, 8 additional nuclear power plants (representative of different US reactor manufacturers and architect-engineers) were surveyed to identify and document the types and amounts of insulation used, location within containment, components insulated, material characteristics, and methods of installation and attachment. These plants were selected to obtain survey information on older plants and supplements information previously reported in NUREG/CR-2403. In addition, a preliminary assessment was made of the potential for migration to the emergency sump of the insulation debris which might be generated as a result of the postulated loss-of-coolant accident

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-09-01

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

Caorso - the first of the new generation of Italian nuclear power plants

International Nuclear Information System (INIS)

Rousek, J.

1976-01-01

The time schedule of the construction, the sub-contractors supplying the main parts of the nuclear power plant, and the technical parameters of the CAORSO power plant are given. The nuclear and the conventional part of the power plant and its connection to the power supply and the preparation of plant operation are described. (J.P.)

U.S. National and regional impacts nuclear plant life extension

International Nuclear Information System (INIS)

Makovick, L.; Fletcher, T.; Harrison, D.L.

1987-01-01

The purpose of this study was to evaluate the economic impacts of nuclear plant life extension on a national and regional level. Nuclear generating capacity is expected to reach 104 Gigawatts (119 units) in the 1994-1995 period. Nuclear units of the 1970 to 1980 vintage are expected to account for 96% of nuclear capacity. As operating licenses expire, a precipitous decline in nuclear capacity results, with an average of 5 gigawatts of capacity lost each year from 2010 to 2030. Without life extension, 95% of all nuclear capacity is retired between the years 2010 and 2030. Even with historically slow growth in electric demand and extensive fossil plant life extension, the need for new generating capacity in the 2010-2030 time period is eight times greater than installed nuclear capacity. Nuclear plant life extension costs and benefits were quantified under numerous scenarios using the DRI Electricity Market Model. Under a wide range of economic assumptions and investment requirements, nuclear plant life extension resulted in a net benefit to electricity consumers. The major source of net benefits from nuclear plant life extension results from the displacement of fossil-fired generating sources. In the most likely case, nuclear plant life extension provides a dollar 200 billion net savings through the year 2030. Regions with a large nuclear capacity share, newer nuclear units and relatively higher costs of alternative fuels benefit the most from life extension. This paper also discusses the importance of regulatory policies on nuclear plant life extension

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

Development of reliability program for emergency diesel generators in domestic nuclear power plants

International Nuclear Information System (INIS)

Kim, Young Ho; Jung, Hyun Jong; Choi, Kwang Hee; Hong, Seoung Yeul

2001-01-01

Surveillance tests of Emergency Diesel Generators (EDGs) in Nuclear Power Plants (NPPs) have been conducted periodically to verify the reliability and integrity of the EDGs, however, it was found that these surveillance methods were so conservative and severe as to accelerate the degradation of the EDGs. Hence, new regulatory guideline, Reg. Guide 1.9 Rev. 3, was established by the U.S. NRC to resolve these problems. But it requires the additional implementation of reliability program of the EDGs to improve the actual reliability of them. In Korea, the EDGs of Yonggwang nuclear units 3 and 4 were the first plant applying new Reg. guide 1.9 rev.3 and implementing EDG reliability program. Furthermore it is expected that new guideline for the EDGs will be applied to other EDGs of Korean NPPs. In this paper, this reliability program is described, and it can be used as a reference for other EDGs in Korean NPPs

Advancements in nuclear plant maintenance programs

International Nuclear Information System (INIS)

Meligi, A.E.; Maras, M.C.

1993-01-01

The viability of the nuclear option as a technology choice for present and future electricity generation will be decided primarily on the basis of operating cost to achieve plant performance objectives. In a nuclear plant, performance is judged not only on availability and output rate but also on safety risk and radiation exposure. Operating, cost is essentially made up of the fuel cost and operation and maintenance (O and M) cost. Over the past decade, the industry average nuclear plant performance has improved significantly; however, this improvement was accompanied by rising O and M cost. The net result was that the nuclear option lost its long-standing economic advantage over the coal option, based on the industry average comparison, around 1987 - with the gap narrowing slightly in the last 2 years. In recent times, gas-fired plants have also become a basis for comparison. The electric generation cost comparisons of various fuel options has led to even greater scrutiny of nuclear plant performance, with the poorer performing plants facing the risk of shutdown. While effective O and M programs improve plant performance, present industry data show that there is no direct correlation between the cost of a plant O and M program and its associated performance. There is a significant number of existing tools and techniques in the O and M area that have proved to be successful and have resulted in significant benefits and payback. This paper presents an overview of the nuclear industry efforts to improve the conduct of O and M activities, describes the basic elements of an effective O and M program, and addresses some of the state-of-the-art tools and techniques to enhance maintenance work planning, training, and procedures

External costs of nuclear-generated electricity

International Nuclear Information System (INIS)

Rotaru, I.; Glodeanu, F.; Popescu, D.; Andrei, V.

2004-01-01

External costs of nuclear power include: future financial liabilities arising from decommissioning and dismantling of nuclear facilities, health and environmental impacts of radioactivity releases in routine operation, radioactive waste disposal and effects of severe accidents. The nuclear energy industry operates under regulations that impose stringent limits to atmospheric emissions and liquid effluents from nuclear facilities as well as requiring the containment and confinement of solid radioactive waste to ensure its isolation from the biosphere as long as it may be harmful for human health and the environment. The capital and operating costs of nuclear power plants and fuel cycle facilities already internalize a major portion of the above-mentioned potential external costs, and these are reflected in the prices paid by consumers of nuclear-generated electricity. The externality related to potential health and environmental impacts of radioactive releases during routine operations have been assessed in a large number of comprehensive studies, in particular the ExternE project that was created in the framework of the European Commission. With regard to effects of severe nuclear accidents, a special legal regime, the third-party liability system, has been implemented to provide limited third party liability coverage in the event of a nuclear accident. The nuclear plant owners are held liable for some specified first substantial part of damages to third parties, and must secure insurance coverage adequate to cover this part. The Government provides coverage for some specified substantial second part of the damages, with any remaining damages to be considered by the national legislation. Thus, the costs of an incident or accident are fully internalized in the costs borne by the nuclear plant owners. Externalities of energy are not limited to environmental and health related impacts, but may result also from macro-economic, policy or strategic factors not reflected

Nuclear Co-Generating Plants for Powering and Heating to Cleaning the Warsaw's Environment

International Nuclear Information System (INIS)

Baurski, J.

2010-01-01

In 2009 the Polish Government made a decision to introduce nuclear power to Poland. Two nuclear power plants (NPPs) will be constructed nearly at the same time - the first unit should start operation in 2020, and by 2030 there should be about 6000 MWe added to the national electrical grid. The Commissioner of the Government was nominated to introduce the Polish Nuclear Power Program (PNPP). One of the four vertically integrated - the biggest energy company (PGE - the Polish Energy Group with headquarters in Warsaw) was appointed to prepare investments. These activities are planned in four stages: I. up to 31.12.2010 - The PNPP will be prepared and the program must then be accepted by the Government. II. 2011 - 2013 - Sites will be determined, and the contract for construction of the first NPP will be closed. III. 2014 - 2015 - Technical specifications will be prepared and accepted according the law. IV. 2016 - 2020 - The first NPP in Poland will be constructed. At present, the Government is receiving proposals from some regions of Poland asking that they be chosen for the NPP. One of the obvious locations for the NPP is a 40-kilometer vicinity of Warsaw (1.8 mln inhabitants). The need for both electric power and heat is increasing because of the rapidly growing town. It gives the extremely valuable chance for a very high thermodynamic efficiency of 80% in co-generation instead of 33% (max 36% for EPR-1600) for NPP generated electric power only. The Warsaw heating system has a capacity of 3950 MWt and is the biggest among EU countries. It is the third biggest in the world. Two NPPs, each of 2 x 1000 MWe could be built on the Vistula River up and down the town. In 2005, UE calculated losses caused by gas emissions at 24 mld eur, and the span of human lives was six months shorter in western countries and 8 months shorter in Poland. Warsaw's atmosphere is very polluted also because there are four heat and power generating plants: three coal and one oil -fired. In these

Atom Mirny: The World’S First Civilian Nuclear Power Plant

International Nuclear Information System (INIS)

Kaiser, Peter; Madsen, Michael

2013-01-01

The world’s first civilian nuclear power plant was commissioned on June 27, 1954 in Obninsk, which was at that time in the Soviet Union, today, the Russian Federation. The Obninsk nuclear power plant generated electricity and supported experimental nuclear research. The Obninsk nuclear power plant operated without incident for 48 years. In September 2002, the last fuel subassembly was unloaded, when the Obninsk nuclear power plant set another first: it became the first nuclear power plant to be decommissioned in Russia

Dukovany nuclear power plant in 1993

International Nuclear Information System (INIS)

1994-01-01

Data on the power generation, nuclear safety, and gaseous and liquid releases into the environment were extracted from the 1993 annual report of the Dukovany nuclear power plant. Operation of the plant was safe and reliable in 1993. Three events were classed as INES category 1. The plant's Failure Commission dealt with 100 events which brought about a total electricity generation loss of 217,624 MWh, corresponding to about 22 reactor-days. Out of this, 26.8 % was due to human error. Three fires occurred at the power plant site. Releases of radioactive aerosols, tritium, noble gases and radioiodine into air and of tritium, corrosion products, and fission products into the aquatic environment were below annual limits. The collective dose equivalent was 1.78 manSv in 1993. (Z.S.). 2 tabs., 11 figs

Operating experience in nuclear power plants

International Nuclear Information System (INIS)

Anon.

1984-01-01

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

Nuclear and conventional baseload electricity generation cost experience

International Nuclear Information System (INIS)

1993-04-01

The experienced costs of electricity generation by nuclear and conventional plants and the expected costs of future plants are important for evaluating the economic attractiveness of various power projects and for planning the expansion of electrical generating systems. The main objective of this report is to shed some light on recent cost experience, based on well authenticated information made available by the IAEA Member States participating in this study. Cost information was provided by Canada (Ontario Hydro), Czechoslovakia, Hungary, India, the Republic of Korea and Spain. Reference is also made to information received from Brazil, China, France, Russia and the United States of America. The part of the report that deals with cost experience is Section 2, where the costs of both nuclear and fossil fired plants are reviewed. Other sections give emphasis to the analysis of the major issues and relevant cost elements influencing the costs of nuclear power plants and to a discussion of cost projections. Many of the conclusions can also be applied to conventional plants, although they are usually less important than in the case of nuclear plants. 1 ref., figs and tabs

Future nuclear power generation

International Nuclear Information System (INIS)

Mosbah, D.S.; Nasreddine, M.

2006-01-01

The book includes an introduction then it speaks about the options to secure sources of energy, nuclear power option, nuclear plants to generate energy including light-water reactors (LWR), heavy-water reactors (HWR), advanced gas-cooled reactors (AGR), fast breeder reactors (FBR), development in the manufacture of reactors, fuel, uranium in the world, current status of nuclear power generation, economics of nuclear power, nuclear power and the environment and nuclear power in the Arab world. A conclusion at the end of the book suggests the increasing demand for energy in the industrialized countries and in a number of countries that enjoy special and economic growth such as China and India pushes the world to search for different energy sources to insure the urgent need for current and anticipated demand in the near and long-term future in light of pessimistic and optimistic outlook for energy in the future. This means that states do a scientific and objective analysis of the currently available data for the springboard to future plans to secure the energy required to support economy and welfare insurance.

Situation of nuclear power generation in Sweden: swaying nuclear energy policy and conversion from nuclear phase-out policy

International Nuclear Information System (INIS)

Kuroda, Yuji

2017-01-01

In Sweden, fossil fuels cannot be produced domestically, and most of them depend on foreign imports. For this reason, together with hydropower generation using abundant water resources, nuclear power generation was introduced and used since the early stage. Nuclear power generation in 2015 reached 35% of total generated power energy. As of 2016, Sweden was steadily constructing the world's second final disposal site of high-level radioactive waste. On the other hand, this country is known as the one that decided nuclear phase-out policy earliest in the world. However, the country's nuclear policy is swaying together with changes in political party power due to election results. In 1980, they decided the policy of abolishing all nuclear power generation by 2010. Thereafter, the nuclear phase-out policy was frozen and maximum 10 units of nuclear plants were accepted. The goal of the latest policy is to allow new construction up to 10 units as replacement, and to use 100% of renewable energy in 2040. However, the year of 2040 is not a deadline for the abolishment of nuclear power generation. In Sweden's public opinion on nuclear power generation, the early abolition was dominant at about 50% during 1986∼1995, but this opinion decreased to about 10% in the 2000s. There is an increasing number of opinions saying that the existing nuclear plants should be continuously operated for a while, and phased out step by step in the future. (A.O.)

Eddy-current tests on operational evaluation of steam generator tubes in nuclear power plants

International Nuclear Information System (INIS)

Lopez, Luiz Antonio Negro Martin; Ting, Daniel Kao Sun

2000-01-01

This paper presents a worldwide research on the technical and economical impacts due to failure in tube bundles of nuclear power plant steam generators. An Eddy current non destructive test using Foucault currents for the inspection and failure detection on the tubes, and also the main type of defects. The paper also presents the signals generated by a Zetec MIZ-40 test equipment. This paper also presents a brief description of an automatic system for data analysis which is under development by using a fuzzy logic and artificial intelligence

Availability improvement factors at Taipower's nuclear power plant system

International Nuclear Information System (INIS)

Chen, J.H.

1985-01-01

Sufficient electricity to meet the needs of a growing industrial economy, is one of the most important factors in the total economic development of a nation. Currently, nuclear power is considered one of the most economical and available sources of energy. To keep pace with Taiwan's rapid economic development, while also observing our government's policy of diversifying the requirements for imported forms of energy, Taiwan Power Company has embarked upon an ambitious of nuclear power plant construction. This paper discusses the improvement of Taiwan's nuclear power plants. At the present time, Taipower has completed three nuclear power plants. Two of these are located in northern Taiwan, along the East China Sea, while the third is on the southern tip of Taiwan, bordering the South China Sea. These three plants, each with two nuclear generating units, comprise a total nuclear generating capacity of 5144 MWe

Economic analysis of nuclear power generation

International Nuclear Information System (INIS)

Song, Ki Dong; Choi, Young Myung; Kim, Hwa Sup; Lee, Man Ki; Moon, Kee Hwan; Kim, Seung Su; Lim, Chae Young

1998-12-01

An energy security index was developed to measure how the introduction of nuclear power generation improved the national security of energy supply in Korea. Using the developed index, a quantitative effort was made to analyze the relationship between the nuclear power generation and the national energy security. Environmental impacts were evaluated and a simplified external cost of a specific coal-fired power plant in Korea was estimated using the QUERI program, which was developed by IAEA. In doing so, efforts were made to quantify the health impacts such as mortality, morbidity, and respiratory hospital admissions due to particulates, SOx, and Nox. The effects of CO 2 emission regulation on the national economy were evaluated. In doing so, the introduction of carbon tax was assumed. Several scenarios were established about the share of nuclear power generation and an effort was made to see how much contribution nuclear energy could make to lessen the burden of the regulation on the national economy. This study re-evaluated the methods for estimating and distributing decommissioning cost of nuclear power plant over lifetime. It was resulted out that the annual decommissioning deposit and consequently, the annual decommissioning cost could vary significantly depending on estimating and distributing methods. (author). 24 refs., 44 tabs., 9 figs

Next Generation Nuclear Plant Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

P. E. MacDonald

2005-01-01

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

Environmental and security challenges of nuclear plants

International Nuclear Information System (INIS)

Omar, A.S.

2014-01-01

The world population increase, the acceleration of global requirement for development and the need to expand energy production, have led to the depletion of natural resources. The international efforts are increasing to get clean, safe and economical energy sources . The electricity generated from nuclear energy considers less polluting and high economic competitiveness as well as reliability and efficiency. The nuclear power plants projects face significant challenges, especially after two major accidents, in Chernobyl 1986 and Fukushima 2011 including the fears of radiation effects, nuclear waste management and nuclear proliferation issues, as well as the lack of public acceptance. So those bodies interested in operating nuclear power plants work to increase nuclear safety standards, review the nuclear facilities safety, know the strict application of laws, seek to prove the economic competitiveness, maintain environmental security, assist in the nonproliferation regime and gain public acceptance. This article discusses the most important environmental and security challenges of nuclear power plants. It highlights the importance of the peaceful uses of nuclear energy as a source of sustainable development and environmental security. It also offers a number of recommendations to support the Arab countries trend towards the inclusion of nuclear energy option within their national programs to generate electricity. (author)

Optimization approaches for treating nuclear power plant problems

International Nuclear Information System (INIS)

Abdelgoad, A.S.A.

2012-01-01

Electricity generation is the process of generating electric energy from other forms of energy. There are many technologies that can be and are used to generate electricity. One of these technologies is the nuclear power. A nuclear power plant (NPP) is a thermal power station in which the heat source is one or more nuclear reactors. As in a conventional thermal power station the heat is used to generate steam which drives a steam turbine connected to a generator which produces electricity. As of February 2nd, 2012, there were 439 nuclear power plants in operation through the world. NPP are usually considered to be base load stations, which are best suited to constant power output. The thesis consists of five chapters: Chapter I presents a survey on some important concepts of the NPP problems. Chapter II introduces the economic future of nuclear power. It presents nuclear energy scenarios beyond 2015, market potential for electricity generation to 2030 and economics of new plant construction. Chapter III presents a reliability centered problem of power plant preventive maintenance scheduling. NPP preventive maintenance scheduling problem with fuzzy parameters in the constraints is solved. A case study is provided to demonstrate the efficiency of proposed model. A comparison study between the deterministic case and fuzzy case for the problem of concern is carried out. Chapter IV introduces a fuzzy approach to the generation expansion planning problem (GEP) in a multiobjective environment. The GEP problem as an integer programming model with fuzzy parameters in the constraints is formulated. A parametric study is carried out for the GEP problem. A case study is provided to demonstrate the efficiency of our proposed model. A comparison study between our approach and the deterministic one is made. Chapter V is concerned with the conclusions arrived in carrying out this thesis and gives some suggestions for further research.

Application of fieldbus techniques in nuclear power plants

International Nuclear Information System (INIS)

Wang Xu; Chen Hang; Yu Shuxin; Zhang Xinli

2012-01-01

The successful application experience of fieldbus techniques in thermal power plants and nuclear power plants are outlined first. And then, the application of fieldbus techniques in domestic 3rd-generation nuclear power plant (NPP) project is discussed. After that, the solution to the potential problems of fieldbus techniques application in NPP is provided. (authors)

Nuclear power plants: 2005 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2006-01-01

Nuclear power plants were available for power supply and under construction, respectively, in 32 countries of the world as per end of 2005. A total of 444 nuclear power plants, i.e. three plants more than at the end of 2004, with an aggregate gross power of approx. 389 GWe and an aggregate net power of 370 GWe, respectively, were in operation in 31 countries. The available capacity of nuclear power plants increased by some 4,5 GWe as a result of the capacities added by the four newly commissioned units of Higashidori 1 (Japan), Shika 2 (Japan), Tarapur 4 (India), and Tianwan 1 (China). In addition, unit A-1 of the Pickering nuclear power station in Canada, with 825 MWe, was restarted after a downtime of several years. Two plants were decommissioned for good in 2005: Obrigheim in Germany, and Barsebaeck 2 in Sweden. 23 nuclear generating units, i.e. one unit more than in late 2004, with an aggregate gross power of approx. 19 GWe were still under construction in nine countries by late 2005. In Pakistan, construction of a new project, Chasnupp 2, was started; in China, construction was begun of two units, Lingao Phase 2, units 3 and 4, and in Japan, the Shimane 3 generating unit is being built. (orig.)

Nuclear energy in medium and long term energy generation of Turkey

International Nuclear Information System (INIS)

Sarici, L. E.; Yilmaz, S.; Guray, B. S.

2001-01-01

In this study; objectives and activities of Nuclear Power Plants Department and Turkish Electricity Generation and Transmission Corporation is briefly mentioned. A brief history of electricity generation, development of Turkish electrical energy sector and development of the installed capacity of country is presented. The history and future perspectives of AKZuyu Nuclear Power Plant Project is sharply outlined. In the light of the current situation in electricity generation and demand projections, importance of nuclear power among the other future electricity generation alternatives of Turkey is underlined

Application of perturbation methods for sensitivity analysis for nuclear power plant steam generators

International Nuclear Information System (INIS)

Gurjao, Emir Candeia

1996-02-01

The differential and GPT (Generalized Perturbation Theory) formalisms of the Perturbation Theory were applied in this work to a simplified U-tubes steam generator model to perform sensitivity analysis. The adjoint and importance equations, with the corresponding expressions for the sensitivity coefficients, were derived for this steam generator model. The system was numerically was numerically solved in a Fortran program, called GEVADJ, in order to calculate the sensitivity coefficients. A transient loss of forced primary coolant in the nuclear power plant Angra-1 was used as example case. The average and final values of functionals: secondary pressure and enthalpy were studied in relation to changes in the secondary feedwater flow, enthalpy and total volume in secondary circuit. Absolute variations in the above functionals were calculated using the perturbative methods, considering the variations in the feedwater flow and total secondary volume. Comparison with the same variations obtained via direct model showed in general good agreement, demonstrating the potentiality of perturbative methods for sensitivity analysis of nuclear systems. (author)

Improved methods for prediction of creep-fatigue in next generation conventional and nuclear plant

International Nuclear Information System (INIS)

Payten, Warwick

2012-01-01

Materials technology poses a major challenge in the design and construction of next generation super critical/ultra super critical power plant (SC/USC) and Generation IV (GenIV) nuclear plant. New plant is expected to have in the order of a 60 year life-time, imposing complex design difficulties in areas of creep rupture and creep fatigue damage. For SC/USC plant, the main goal is the enhancement of performance by raising the steam pressure and temperatures. In order to achieve these goals materials with acceptable creep rupture strength at design temperatures and pressures must be used. In GenIV designs, the issue is more complex, with both low and high tempera-ture designs. A key requirement in the majority of the designs, however, will be acceptable resistance to creep rupture, fatigue cracking, creep fatigue interactions, with the additional effects of void swelling and irradiation creep. The accumulation of creep fatigue damage over time in both SC/USC and GenIV plant will be one of the principal damage mechanisms. This will eventually lead to crack initiation in critical high temperature equipment. Hence, improved knowledge of creep and fatigue interactions is a necessary development as components in power-generating plants move to operate at high temperature under cyclic conditions. The key to safe, reliable operation of these high-energy plants will depend on understanding the factors that affect damage initiation and propagation, as well as developing and validating technologies to predict the accumulation of damage in systems and components.

Slovak Electric, plc, Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

2000-01-01

In this popular scientific brochure a brief description of history construction of Bohunice Nuclear Power Plant is presented. The chart of electricity generation in WWER 440/V-213 nuclear power plant is described. Operation and safety improvements at Mochovce NPP as well as environment protection are presented. Basic data of Mochovce NPP are included

Slovak Electric, plc, Bohunice Nuclear Power Plant

International Nuclear Information System (INIS)

1999-01-01

A brief account of activities carried out by the Bohunice Nuclear Power Plant in 1998 is presented. These activities are reported under the headings: (1) Operation and electric power generation; (2) Nuclear and radiation safety; (3) Maintenance and scheduled refuelling out-gages; (4) Investment and WWER units upgrading; (5) Power Plants Personnel; (6) Public relations

Development of a new generation of ion exchange resin for nuclear and fossil power plant

International Nuclear Information System (INIS)

Tsuzuki, Shintaro; Tagawa, Hidemi; Yamashita, Futoshi; Okamoto, Ryutaro

2008-01-01

It is required to maintain water quality supplied to steam generator to the water designed based on its water chemistry in order to keep the sound operation of nuclear power plants or fossil power plants. Condensate Polishing Plant (CPP) is installed for removing ions in the water which uses a mixed bed of cation exchange resin and anion exchange resin. We have developed new generation of CPP resin. The product is a unique combination of super high exchange capacity cation exchange resin and high fouling resistant anion exchange resin. The CPP resin has been used in many power plants. Amberjet 1006 was developed as a cation exchange resin with high oxidative stability, high operational capacity and New IRA900CP was developed as an anion exchange resin with high fouling resistant to leachables released out of cation exchange resin by oxidative degradation over the service period. The novel CPP resin was first used in 2000 and has now been used in many power plants in Japan. The CPP resin has been giving excellent quality of water. (author)

Siemens's spectrum of deliveries and services for nuclear power plants

International Nuclear Information System (INIS)

2011-01-01

In 2001, Siemens and Framatome merged their nuclear activities in the present Areva NP joint venture. Siemens has since focused on the construction and further development of conventional power plants and on the so-called conventional island (CI), the non-nuclear part of a nuclear power plant, i.e. the steam turbine, generator, and plant I and C systems, and also on service for the conventional part of nuclear power plants. Its role as a minority shareholder in Areva NP constrained Siemens. For this reason, the company in January 2009 decided to terminate its interest in Areva NP effective January 30, 2012. By January 2012 at the latest, Siemens will transfer to the majority shareholder Areva, holding 66 percent of the shares, its interest in the joint venture. For the time being, the joint venture still entails certain limitations to Siemens's activities in the nuclear field. Its delivery of the conventional island for the Olkiluoto 3 (OL3) nuclear power plant in Finland confirms the company's know-how in power plant construction. When commissioned, its 1,720 MW power will make OL3 the world's largest nuclear generating unit. The turbo-generator of the CI comprises a double-flow HP turbine and a 6-flow LP turbine. The driven 4-pole generator with a power of up to 2,200 MVA consists of a water-cooled stator and a hydrogen-cooled rotor. (orig.)

Electricity Generation Through the Koeberg Nuclear Power Station of Eskom in South Africa

International Nuclear Information System (INIS)

Dladla, G.; Joubert, J.

2015-01-01

The poster provides information on the process of nuclear energy generation in a nuclear power plant in order to produce electricity. Nuclear energy currently provides approximately 11% of the world’s electricity needs, with Koeberg Nuclear Power Station situated in the Western Cape providing 4.4% of South Africa’s electricity needs. As Africa’s first nuclear power station, Koeberg has an installed capacity of 1910 MW of power. Koeberg’ s total net output is 1860 MW. While there are significant differences, there are many similarities between nuclear power plants and other electrical generating facilities. Uranium is used for fuel in nuclear power plants to make electricity. With the exception of solar, wind, and hydroelectric plants, all others including nuclear plants convert water to steam that spins the propeller-like blades of a turbine that spins the shaft of a generator. Inside the generator coils of wire and magnetic fields interact to create electricity. The energy needed to boil water into steam is produced in one of two ways: by burning coal, oil, or gas (fossil fuels) in a furnace or by splitting certain atoms of uranium in a nuclear energy plant. The uranium fuel generates heat through a controlled fission process fission, which is described in this poster presentation. The Koeberg Nuclear Power Station is a Pressurised water reactor (PWR). The operating method and the components of the Koeberg Power Station are also described. The nuclear waste generated at a nuclear power station is described under three headings— low-level waste, intermediate-level waste and used or spent fuel, which can be solid, liquid or gaseous. (author)

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

Efforts onto electricity and instrumentation technology for nuclear power generation

International Nuclear Information System (INIS)

Hayakawa, Toshifumi

2000-01-01

Nuclear power generation shares more than 1/3 of all amounts of in-land generation at present, as a supplying source of stable electric energy after 2000 either. As a recent example of efforts onto electricity and instrumentation technology for nuclear power generation, there are, on instrumentation control system a new central control board aiming at reduction of operator's load, protection of human error, and upgrading of system reliability and economics by applying high level micro-processor applied technique and high speed data transfer technique to central monitoring operation and plant control protection, on a field of reactor instrumentation a new digital control rod position indicator improved of conventional system on a base of operation experience and recent technology, on a field of radiation instrumentation a new radiation instrumentation system accumulating actual results in a wide application field on a concept of application to nuclear power plant by adopting in-situ separation processing system using local network technique, and on a field of operation maintenance and management a conservation management system for nuclear generation plant intending of further effectiveness of operation maintenance management of power plant by applying of operation experience and recent data processing and communication technology. And, in the large electric apparatus, there are some generators carried out production and verification of a model one with actual size in lengthwise dimension, to correspond to future large capacity nuclear power plant. By this verification, it was proved that even large capacity generator of 1800 MVA class could be manufactured. (G.K.)

Nuclear energy generation and the safety criteria for Brazilian power plants

International Nuclear Information System (INIS)

Silva, Gustavo Brandão e

2016-01-01

The purpose of this paper is to show how the use of nuclear technology can help to diversify the national electricity matrix in a sustainable and efficient way. For this, an analysis of the current situation of the Brazilian electric sector will be made, exposing its fragilities and highlighting the advantages of the nuclear source as an alternative to integrate the necessary thermoelectric base to the reliable supply of electricity in the country. In addition, the objective of the work is to detail the process of exploiting atomic energy in Brazil from raw material mining, through the stages involving the manufacture of nuclear fuel, to the current operation and situation of Brazilian power plants. By taking the Angra 2 Nuclear Power Plant as a case study, the safety criteria adopted in its design and operation will be highlighted. Particular attention will also be given to the electric supply alternatives and to the active safety systems of the plant

Next Generation Nuclear Plant Pre-Conceptual Design Report

International Nuclear Information System (INIS)

Larry Demick; Doug Vandel

2007-01-01

The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear based technology can provide high-temperature process heat (up to 950 C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications. The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively1 safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to current and advanced light water reactors (LWRs). In the Energy Policy Act of 2005 (EPAct), the Department of Energy (DOE) was tasked with providing a demonstration of this HTGR technology to economically and reliably produce electricity and hydrogen by the year 2021. As the lead nuclear technology development laboratory of the DOE, the Idaho National Laboratory (INL) has initiated the work necessary to complete this task. The EPAct also stipulated that the task should be undertaken in partnership with the industrial end users of the technology. To that end, a working group has been assembled consisting of suppliers of the technology, nuclear plant owner/operators, other supportive technology companies, and potential end users. The objective of the working group is to form an Alliance that would provide the private sector perspective and direction for completion of the NGNP in partnership with the DOE. The Alliance will support the selection of the specific operating conditions and configuration for NGNP to ensure it meets private sector expectations, commence

Occupational exposures and practices in nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.

1989-01-01

As the first generation of commercial nuclear power comes to a close, it is timely to consider the status of occupational exposure in the power generation industry, that is, the collective occupational radiation doses received by workers in nuclear power plants. The picture is surprising. One might have thought that as newer, larger, and more modern plants came on line, there would be a significant decrease in exposure per unit of electricity generated. There is some indication that this is now happening. One might also have thought that the United States, being a leader in the development of nuclear power, and in the knowledge, experience and technology of nuclear radiation protection, would have the greatest success in controlling exposure. This expectation has not been fulfilled. 32 refs., 4 figs., 5 tabs

Third generation of nuclear power development

International Nuclear Information System (INIS)

Townsend, H.D.

1988-01-01

Developing nations use the nuclear plant option to satisfy important overall national development objectives, in addition to providing economical electric power. The relative importance of these two objectives changes as the nuclear program develops and the interim milestones are reached. This paper describes the three typical stages of nuclear power development programs. The first and the second generations are development phases with the third generation reaching self sufficiency. Examples are presented of European and Far East countries or regions which have reached or are about to step into the third generation phase of development. The paper concludes that to achieve the objectives of a nuclear power self sufficiency, other than merely filling the need of economical electric power, a careful technology transfer plan must be followed which sets realistic and achievable goals and establishes the country as a reliable and technically competent member of the nuclear power industry

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

International Nuclear Information System (INIS)

Shi Ji; Jiang Mingyu; Ma Yunqin

2004-01-01

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

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

Nuclear Power Plants and Sustainable Development on a Liberalized Market

International Nuclear Information System (INIS)

Androcec, I.; Stanic, Z.; Tomsic, Z.

2002-01-01

Finding a way to generate electricity so as to satisfy the terms of sustainable development of the entire society is the only way which will secure safe energy future. If we talk about energy in the context of sustainable development, one of the most important element is environmental protection. Since CO 2 emissions stemming from electricity generation have predominant impact on climate change, one of the options for reducing emissions is the use of fuels without carbon, such as e.g. nuclear fuel. The future of nuclear power plants was considered in view of: nuclear fuel supply; potential impact of fuel cycle on environment, power plant operation, decommissioning and secondary products from electricity generation; and the entire nuclear power plant economy. Nuclear power plants were also examined in the context of the Kyoto Protocol stipulating reduction of greenhouse gases emissions. Nuclear power plants can not reduce CO 2 emissions in a short-term because they already operate with maximum output, but in a long-run they can play a significant role. This paper is aiming to analyse the role of nuclear power plants in long term environmental sustainability in electricity sector reform (liberalisation, deregulation, privatisation) in small or medium sized power supply systems. Nuclear power plants are associated with certain environmental aspects which will be taken into account. A comparison will be made through externalities with other energy resources, especially fossil fuels, which are prevailing energy resources, considering possible use of nuclear power plants in the countries with small and medium-size grids. It will be given an example of the role of NPP Krsko on air emissions reduction in Croatia. (author)

A connection of the steam generator feedwater section of WWER type nuclear power plants

International Nuclear Information System (INIS)

Matal, O.; Sadilek, J.

1989-01-01

In the feedwater piping of each steam generator, a plate for additional water pressure reduction is inserted before the first closing valve. During a steady water flow, the plate gives rise to a constant hydraulic resistance, bringing about steady reduction of the feedwater pressure; this also contributes to a stabilization of the feedwater flow rate into the steam generator. The control valve thus is stressed by minimal hydrodynamic forces. In this manner its load is decreased, its vibrations are damped, and the frequency of failures - and thereby the frequency of the nuclear power plant unit outages -is reduced. (J.P.). 1 fig

Nuclear power generation: challenge in the 1980s

International Nuclear Information System (INIS)

Eklund, S.A.

1981-01-01

In the lecture ''Nuclear power generation - challenge in the 1980s'', attempt is made to predict the events arising in 1980s on the basis of the data available in the International Atomic Energy Agency. By the term ''challenge'', emphasis is placed on the potentiality of nuclear power for solving the world energy problem. This is indicated clearly by nuclear power currently accounting for 8%, of the total power generation in the world. The explanation in the above connection with figures and tables is made, including geographical distribution of reactors, nuclear power generation and total power generation in various countries, future capacity of nuclear power generation, situation of reactor operation, future installation of nuclear power plants, uranium demand/supply situation, spent fuel storage, etc. Then, discussion and analysis are made on such problems as waste management, economy, safety, and safeguards. (J.P.N.)

Problems facing a first nuclear power plant

International Nuclear Information System (INIS)

Diaz, E.

1986-01-01

Requirement of nuclear power generation. Reason for considering a nuclear power programme. Decision to 'go nuclear'. Existing antecedents in the country (nuclear research institution, conventional generating plants, other nuclear utilities). - First organizational steps. Feasibility studies. Site selection and power module. Eventual reactor type decision. Site approval. - Pre-purchasing activities. Eventual selection of a consultant. Domestic participation capabilities. Pre-qualification bids. - Definition of contract type and scopes. Turn-key/non-turn-key. Architect Engineer organization. Bidding documentation. Financing. Warranties. Role of the owner. Licensing procedures and regulations. (orig./GL)

Stress corrosion cracking of steam generator tube and primary pipe in PWR type nuclear power plants

International Nuclear Information System (INIS)

Zhang Weiguo; Gao Fengqin; Zhou Hongyi

1993-01-01

The behavior of stress corrosion cracking (SCC) is studied by slow strain rate test (SSRT), constant load test (CLT) and low frequency cyclic loading test (LFCLT). The purpose of these tests is to get the test data for evaluating the integrity of pressurized boundary of pipes in Qinshan and Guangdong nuclear power plants. Tested materials are 316 nuclear grade stainless steel (SS) for primary pipes in welded heat affected zone (WHAZ) and steam generator tubes, such as Incoloy-800, Inconel-600, Inconel-690 and 321 SS which are used for steam generator in PWR. The effects of material metallurgy, shot-peening treatment, tensile load, strain rate, cyclic load and water chemistry on the behavior of SCC are investigated

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators. 2011 Update

International Nuclear Information System (INIS)

2011-11-01

generator of the PWR, WWER and CANDU nuclear power plants. The objective of this report is to update and supersede IAEA-TECDOC-981 in order to provide current ageing management guidance for PWR, WWER and CANDU steam generators to all involved in the operation and regulation of nuclear power plants and thus to help ensure steam generator integrity in IAEA Member States throughout their entire service life.

Cost of nuclear power generation judged by power rate

International Nuclear Information System (INIS)

Hirai, Takaharu

1981-01-01

According to estimation guidance, power rates in general are the proper cost plus the specific compensation and adjustment addition. However, the current system of power rates is of power-source development promotion type involving its tax. The structure of power rate determination must be restudied now especially in connection of nuclear power generation. The cost of nuclear power generation as viewed from power rate is discussed as follows: the fear of military application of power plants, rising plant construction costs, the loophole in fuel cost calculation, unreasonable unit power cost, depreciation and repair cost, business compensation, undue business compensation in nuclear power, the costs of nuclear waste management, doubt concerning nuclear power cost, personnel, pumping-up and power transmission costs in nuclear power, energy balance analysis, nuclear power viewed in entropy, the suppression of power consumption. (J.P.N.)

Thermohidraulic model for a typical steam generator of PWR Nuclear Power Plants

International Nuclear Information System (INIS)

Braga, C.V.M.

1980-06-01

A model of thermohidraulic simulation, for steady state, considering the secondary flow divided in two parts individually homogeneous, and with heat and mass transferences between them is developed. The quality of the two-phase mixture that is fed to the turbine is fixed and, based on this value, the feedwater pressure is determined. The recirculation ratio is intrinsically determined. Based on this model it was developed the GEVAP code, in Fortran-IV language. The model is applied to the steam generator of the Angra II nuclear power plant and the results are compared with KWU'S design parameters, being considered satisfactory. (Author) [pt

Application of fatigue monitoring system in PWR nuclear power plant

International Nuclear Information System (INIS)

Piao Lei

2014-01-01

Fatigue failure is one form of equipment failure of nuclear power plant, influencing equipment lifetime and lifetime extension. Fatigue monitoring system can track real thermal transient at fatigue sensitive components, establish a basis for fatigue analyses based on realistic operating loads, identify unexpected operational transients, optimize the plant behavior by improved operating modes, provide supporting data for lifetime management, enhance security of plant and reduce economical loss. Fatigue monitoring system has been applied in many plants and is required to be applied in Generation-III nuclear power plant. It is necessary to develop the fatigue monitoring system with independent intellectual property rights and improve the competitiveness of domestic Generation-III nuclear power technology. (author)

World nuclear power generation market and prospects of industry reorganization

International Nuclear Information System (INIS)

Murakami, Tomoko

2007-01-01

In late years there are many trends placing nuclear energy with important energy in various countries in the world due to a remarkable rise to an energy price, importance of energy security and a surge of recognition to a global environment problem. Overseas nuclear industry's acquisition by a Japanese nuclear power plant maker and its capital or business tie-up with an overseas company, were announced in succession in 2006. A nuclear power plant maker has played an extremely important role supporting wide technology in all stages of a design, construction, operation and maintenance in a nuclear power generation business. After having surveyed the recent trend of world nuclear power generation situation, a background and the summary of these acquisition/tie-ups made were investigated and analyzed to consider the influence that movement of such an industry gives a world nuclear power generation market. (T. Tanaka)

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

High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant

International Nuclear Information System (INIS)

Beck, J.M.; Collins, J.W.; Garcia, C.B.; Pincock, L.F.

2010-01-01

High Temperature Gas Reactors (HTGR) have been designed and operated throughout the world over the past five decades. These seven HTGRs are varied in size, outlet temperature, primary fluid, and purpose. However, there is much the Next Generation Nuclear Plant (NGNP) has learned and can learn from these experiences. This report captures these various experiences and documents the lessons learned according to the physical NGNP hardware (i.e., systems, subsystems, and components) affected thereby.

Regional comparison of nuclear and fossil electric power generation costs

International Nuclear Information System (INIS)

Bowers, H.I.

1984-01-01

Nuclear's main disadvantages are its high capital investment cost and uncertainty in schedule compared with alternatives. Nuclear plant costs continue to rise whereas coal plant investment costs are staying relative steady. Based on average experience, nuclear capital investment costs are nearly double those of coal-fired generation plants. The capital investment cost disadvantage of nuclear is balanced by its fuel cost advantages. New base load nuclear power plants were projected to be competitive with coal-fired plants in most regions of the country. Nuclear power costs wre projected to be significantly less (10% or more) than coal-fired power costs in the South Atlantic region. Coal-fired plants were projected to have a significant economic advantage over nuclear plants in the Central and North Central regions. In the remaining seven regions, the levelized cost of power from either option was projected to be within 10%. Uncertainties in future costs of materials, services, and financing affect the relative economics of the nuclear and coal options significantly. 10 figures

Nuclear plant life - A business decision

International Nuclear Information System (INIS)

Joosten, J.K.

1995-01-01

Regarding the future of the nuclear power option, many scenarios have been put forth over the years. The most commonly accepted projections for installed nuclear capacity show it growing at a rate of about 2% per year throughout the next few decades. These projections appear modes on the surface. However, underlying the projections are critical assumptions and sometimes misconceptions about the lifetimes of existing reactors and how they are determined. The notion of a 40 year plant life is very common. Consequently, many projections start either with the assumption that no plants will be retired in the near terms or with the assumption that each retired plant will be replaced by another nuclear plant after 40 years. Effectively, these assumptions yield future projections for installed capacity that might be characterized as low growth, medium growth and high growth scenarios - or grow, grow, grow. The question remains as to whether or not these assumptions accurately model the driving forces and constraints to nuclear development. After all, there is no scientific basis for believing that all plants, PWRs BWRs, RBMKs, etc., should have the same 40 year life. Most power plant owners purchase the plant for the main reason of supplying electrical power to their consumer. For these owners, electricity production is a day to day commercial activity with various alternatives on how to achieve the prime objective. The decision of which electricity generation alternative to select (gas, coal, nuclear or renewable energy) and how long to operate the plant before replacing it with a new one is essentially a business decision. The paper discusses ageing, the nuclear plant life decision process, the factors which influence the decision and their ramifications regarding the near term growth of nuclear power capacity. The modelling of nuclear plant lifetimes is also discussed. (author). 5 refs, 10 figs, 1 tab

New Temperature References and Sensors for the Next Generation of Nuclear Power Plants

International Nuclear Information System (INIS)

Sadli, M.; Deuze, T.; Failleau, G.; Mokdad, S.-A.; Podesta, M. de; Edwards, G.; Elliott, C.-J.; Pearce, J.-V.; Sutton, G.; Del Campo, D.; Garcia-Izquierdo, C.; Fourrez, S.; Laurie, M.

2013-06-01

In preparation for the new challenges posed by the higher temperature environments which are likely to be encountered in the next generation of nuclear power plants, to maintain the safety and to ensure the long-term reliability of such plants, it is crucial that new temperature sensors and methods for in-situ measurement are investigated and developed. This is the general objective of the first work package of the joint research project, ENG08 MetroFission, funded in the framework of the European metrology research program. This paper will review the results obtained in developing and testing new temperature sensors and references during the course of the project. The possible continuation of these activities in the future is discussed. (authors)

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Saurwein, John

2011-07-15

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

International Nuclear Information System (INIS)

Saurwein, J.

2011-01-01

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

A large capacity turbine generator for nuclear power generation

International Nuclear Information System (INIS)

Maeda, Susumu; Miki, Takahiro; Suzuki, Kazuichi

2000-01-01

In future large capacity nuclear power plant, capacity of a generator to be applied will be 1800 MVA of the largest class in the world. In response to this, the Mitsubishi Electric Co., Ltd. began to carry out element technology verification of a four-pole large capacity turbine generator mainly using upgrading technique of large capacity, since 1994 fiscal year. And, aiming at reliability verification of the 1800 MVA class generator, a model generator with same cross-section as that of an actual one was manufactured, to carry out some verifications on its electrified tests, and so on. Every performance evaluation result of tests on the model generator were good, and high reliability to design and manufacturing technique of the 1800 MVA class generator could be verified. In future, on the base of these technologies, further upgrading of reliability on the large capacity turbine generator for nuclear power generation is intended to be carried out. (G.K.)

Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

International Nuclear Information System (INIS)

1982-09-01

The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

A hypothesis generation model of initiating events for nuclear power plant operators

International Nuclear Information System (INIS)

Sawhney, R.S.; Dodds, H.L.; Schryver, J.C.; Knee, H.E.

1989-01-01

The goal of existing alarm-filtering models is to provide the operator with the most accurate assessment of patterns of annunciated alarms. Some models are based on event-tree analysis, such as DuPont's Diagnosis of Multiple Alarms. Other models focus on improving hypothesis generation by deemphasizing alarms not relevant to the current plant scenario. Many such models utilize the alarm filtering system as a basis of dynamic prioritization. The Lisp-based alarm analysis model presented in this paper was developed for the Advanced Controls Program at Oak Ridge National Laboratory to dynamically prioritize hypotheses via an AFS by incorporating an unannunciated alarm analysis with other plant-based concepts. The objective of this effort is to develop an alarm analysis model that would allow greater flexibility and more accurate hypothesis generation than the prototype fault diagnosis model utilized in the Integrated Reactor Operator/System (INTEROPS) model. INTEROPS is a time-based predictive model of the nuclear power plant operator, which utilizes alarm information in a manner similar to the human operator. This is achieved by recoding the knowledge base from the personal computer-based expert system shell to a common Lisp structure, providing the ability to easily modify both the manner in which the knowledge is structured as well as the logic by which the program performs fault diagnosis

Plant polyphenols mobilize nuclear copper in human peripheral lymphocytes leading to oxidatively generated DNA breakage: implications for an anticancer mechanism.

Science.gov (United States)

Shamim, Uzma; Hanif, Sarmad; Ullah, M F; Azmi, Asfar S; Bhat, Showket H; Hadi, S M

2008-08-01

It was earlier proposed that an important anti-cancer mechanism of plant polyphenols may involve mobilization of endogenous copper ions, possibly chromatin-bound copper and the consequent pro-oxidant action. This paper shows that plant polyphenols are able to mobilize nuclear copper in human lymphocytes, leading to degradation of cellular DNA. A cellular system of lymphocytes isolated from human peripheral blood and comet assay was used for this purpose. Incubation of lymphocytes with neocuproine (a cell membrane permeable copper chelator) inhibited DNA degradation in intact lymphocytes. Bathocuproine, which is unable to permeate through the cell membrane, did not cause such inhibition. This study has further shown that polyphenols are able to degrade DNA in cell nuclei and that such DNA degradation is inhibited by neocuproine as well as bathocuproine (both of which are able to permeate the nuclear pore complex), suggesting that nuclear copper is mobilized in this reaction. Pre-incubation of lymphocyte nuclei with polyphenols indicates that it is capable of traversing the nuclear membrane. This study has also shown that polyphenols generate oxidative stress in lymphocyte nuclei which is inhibited by scavengers of reactive oxygen species (ROS) and neocuproine. These results indicate that the generation of ROS occurs through mobilization of nuclear copper resulting in oxidatively generated DNA breakage.

Determination of leveled costs of electric generation for gas plants, coal and nuclear; Determinacion de costos nivelados de generacion electrica para plantas de gas, carbon y nucleares

Energy Technology Data Exchange (ETDEWEB)

Alonso V, G.; Palacios H, J.C.; Ramirez S, J.R.; Gomez, A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: galonso@nuclear.inin.mx

2005-07-01

The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

Nuclear economics 2000: Deterministic and probabilistic projections of nuclear and coal electric power generation costs for the year 2000

International Nuclear Information System (INIS)

Williams, K.A.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

1987-06-01

The total busbar electric generating costs were estimated for locations in ten regions of the United States for base-load nuclear and coal-fired power plants with a startup date of January 2000. For the Midwest region a complete data set that specifies each parameter used to obtain the comparative results is supplied. When based on the reference set of input variables, the comparison of power generation costs is found to favor nuclear in most regions of the country. Nuclear power is most favored in the northeast and western regions where coal must be transported over long distances; however, coal-fired generation is most competitive in the north central region where large reserves of cheaply mineable coal exist. In several regions small changes in the reference variables could cause either option to be preferred. The reference data set reflects the better of recent electric utility construction cost experience (BE) for nuclear plants. This study assumes as its reference case a stable regulatory environment and improved planning and construction practices, resulting in nuclear plants typically built at the present BE costs. Today's BE nuclear-plant capital investment cost model is then being used as a surrogate for projected costs for the next generation of light-water reactor plants. An alternative analysis based on today's median experience (ME) nuclear-plant construction cost experience is also included. In this case, coal is favored in all ten regions, implying that typical nuclear capital investment costs must improve for nuclear to be competitive

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

Nuclear Energy In Switzerland: It's going ahead. Challenges For The Swiss Nuclear Society Young Generation Group

International Nuclear Information System (INIS)

Streit, Marco; Bichsel, Thomas; Fassbender, Andre; Horvath, Matthias

2008-01-01

Swiss energy policy is focused on generating domestic electric power without combusting fossil fuels for already four decades. Roughly 60% of the electricity is generated in hydroelectric plants, which is possible due to the country's favourable topography; the remaining 40% are produced by the country's five nuclear power plants (NPPs). As in any other country nuclear power has its enemies in Switzerland. Due to the direct democracy system in Switzerland the nuclear opposition has a lot of possibilities to disturb the energy policy. Since 1969, when the first Swiss nuclear power plant went online, four plebiscites were held on the issue of civil use of nuclear energy. Four times Swiss citizens voted in favour of further operation of the existing plants also in the latest battle for nuclear energy, which was won in 2003. In 2005 and 2006 several Swiss studies about the future energy situation, especially the electricity situation, have been published. All off them show clearly that there will be a big gab around the year 2020 when the oldest three nuclear power plants will fade out. A public debate was started, how to solve the problem. Beside others, building new nuclear power plants was mentioned and discussed rationally. In 2007 the energy police of the Swiss government changed into a more nuclear friendly position and at the end of the same year some electricity companies lunched a new build program. Hosting the International Youth Nuclear Congress 2008 (IYNC 2008) in Switzerland seems to be just the right moment for the nuclear industry in our country. The slightly changed surroundings effected the organization of Swiss Nuclear Society (SNS) and SNS Young Generation Group (SNSYG) and enlarged the fields of activities for SNSYG. Those activities mentioned in the previous chapters will be developed in the future. The discussion about new builds in Switzerland has started and because of that more nuclear activities in Switzerland will occur. And surely there will

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)

Young generation in Romanian nuclear system - Romanian nuclear organizations implication in nuclear knowledge management at University 'Politehnica' of Bucharest - Results and expectations

International Nuclear Information System (INIS)

Ghizdeanu, E.N.; Dumitrescu, M.C.; Budu, A.R.; Pavelescu, A.O.

2004-01-01

The knowledge management should be assumed by the major players within the nuclear community: government, industry and university. Starting from these problems this article gives an overview about Romanian nuclear knowledge management and the Young Generation implications. In Romania there are many government and non-government nuclear institutions such: CNCAN (Romanian Regulatory Body), ROMATOM (Romanian Atomic Forum), AREN (Romanian 'Nuclear Energy' Association), and companies: SNN ('Nuclearelectrica' SA National Company), CITON (Centre of Technology and Engineering for Nuclear Projects), SCN (Institute for Nuclear Research), ROMAG - PROD (Romanian Heavy Water Plant). All these institutes and companies are sustaining the national nuclear program and promoting the new technologies in the nuclear industry according with CNCAN and ROMATOM regulations. University 'POLITEHNICA' of Bucharest - Power Engineering Faculty - through Nuclear Power Plant Department is the promoter of nuclear knowledge management. It is implied in assuring and maintaining a high-quality training for young staff. Young Generation is implicated in nuclear knowledge management through University 'Politehnica' of Bucharest - Power Engineering Faculty - Nuclear Power Plant Department and AREN (Romanian 'Nuclear Energy' Association). Young Generation Department has special educational programs for attracting and supporting students. It provides adequate information and interacts with potential students. Moreover the article gives results about Romanian nuclear engineers since 1970 till now. An analysis of these data is done. Also it is discussed how University 'Politehnica' of Bucharest, the Romanian Government and the Industry work together to co-ordinate more effectively their efforts to encourage the young generation. (author)

Erosion-corrosion entrainment of iron-containing compounds as a source of deposits in steam generators used at nuclear power plants equipped with VVER reactors

Science.gov (United States)

Tomarov, G. V.; Shipkov, A. A.

2011-03-01

The main stages and processes through which deposits are generated, migrate, and precipitate in the metal-secondary coolant system of power units at nuclear power plants are analyzed and determined. It is shown that substances produced by the mechanism of general erosion-corrosion are the main source of the ionic-colloid form of iron, which is the main component of deposits in a steam generator. Ways for controlling the formation of deposits in a nuclear power plant's steam generator are proposed together with methods for estimating their efficiency.

Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary.

ELECNUC. Nuclear power plants in the world - 2012 edition, Status on 2011-12-31

International Nuclear Information System (INIS)

2012-01-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2011 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2011/01/01; Worldwide status of nuclear power plants (12/31/2011); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2011; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear powe plants by country at the end 2011; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2011; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2011; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2011; Long term shutdown units at 12/31/2011; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

The Carem reactor: Bridging the gap to nuclear power generation

International Nuclear Information System (INIS)

Ordonez, J.P.

1998-01-01

An idea is presented as an alternative for the introduction of nuclear power in presently non-nuclear countries. This idea involves going through an intermediate step between the traditional research reactor and the first commercial nuclear power plant. This intermediate step would consist of a very small nuclear power plant, with the principal goal of gaining in experience in the country on all the processes involved in introducing commercial nuclear generation. (author)

Trial application of reliability technology to emergency diesel generators at the Trojan Nuclear Power Plant

International Nuclear Information System (INIS)

Wong, S.M.; Boccio, J.L.; Karimian, S.; Azarm, M.A.; Carbonaro, J.; DeMoss, G.

1986-01-01

In this paper, a trial application of reliability technology to the emergency diesel generator system at the Trojan Nuclear Power Plant is presented. An approach for formulating a reliability program plan for this system is being developed. The trial application has shown that a reliability program process, using risk- and reliability-based techniques, can be interwoven into current plant operational activities to help in controlling, analyzing, and predicting faults that can challenge safety systems. With the cooperation of the utility, Portland General Electric Co., this reliability program can eventually be implemented at Trojan to track its effectiveness

Current Status and Future Outlook of Nuclear Power Generation in Japan

Energy Technology Data Exchange (ETDEWEB)

Suzuki, Yasuro; Yoshii, Ryosuke

2007-07-01

For Japan, a country poor in natural resources, in light of the tough energy situation in recent times, a National Energy Strategy with energy security at its core was established in May 2006. The key point of the Strategy is nuclear power generation, and the aim is to ensure that nuclear power generation continues to account for 30 to 40 percent or more of total electricity generated even after 2030. The first step to achieving this goal is to make maximum use of existing plants (55 plants, 49580MWe), and the aim is to achieve a 60-year service life by making improvements to plant operation and maintenance, such as extending current monitoring and maintenance of plant condition, and the implementation of plant aging management. In Japan, plant construction has been continuous since the 1970s. The current new plant construction plan (13 plants, 17230MWe) is to be achieved with a concerted, cohesive national effort. In addition, in order to complete the nuclear fuel cycle, a reprocessing plant is being constructed strictly for peaceful use, and construction of a site for disposing of high-level radioactive waste is also proceeding. Development of the next generation light water reactors and fast breeder reactor cycle is also underway. (auth)

British Nuclear Fuels plc's effluent plant services building

International Nuclear Information System (INIS)

Williams, L.

1990-01-01

The new Effluent Plant Services building (EPSB) on the Sellafield Nine Acre Site was built by Costain Engineering Limited for British Nuclear Fuels Limited. The EPSB is dedicated to a new generation of nuclear waste treatment plants, aimed at reducing discharges into the Irish Sea and other environmental impacts by removing actinides from liquid effluents and decontaminating waste solvents. This article describes the design, construction and operation of the plant. (UK)

Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 3

International Nuclear Information System (INIS)

G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

2006-01-01

This is the 2006 update (Revision 3) of the NGNP Materials Research and Development Program Plan. This law established that the U.S Department of Energy (DOE) Secretary of Energy shall establish a ''Next Generation Nuclear Plant'' (NGNP) project. The NGNP project named in the Act was given the following attributes and guiding principles to manage its development: (1) The NGNP consists of research, development, design (R and DD), construction, and operation of a prototype reactor to generate electricity and hydrogen; (2) The project shall be managed by the DOE Office of Nuclear Energy; (3) The Idaho National Laboratory (INL) shall be the lead DOE laboratory for the NGNP; (4) The INL shall establish collaborations with selected institutions of higher education, other research institutes and international researchers; (5) The INL shall organize an industrial consortium of partners for cost-shared R and DD, construction; (6) The project shall be sited at the INL; (7) The project shall be licensed by the Nuclear Regulatory Commission (NRC) and by July, 2008 the NRC and DOE shall jointly submit a licensing strategy to Congress; (8) The project shall be organized to maximize technical interchange with the nuclear power industry, nuclear power plant construction firms, the chemical process industry and to seek international cooperation, participation and contributions; (9) The Nuclear Energy Research Advisory Committee (NERAC) shall review all program plans for the NGNP; (10) Phase 1 of the project (selection of hydrogen production technology, conduct R and DD and initial design activities) shall be completed no later than September 30, 2011; (11) Phase 2 of the project (continue R and DD, develop final design, apply for a license, construct and start operations) shall be completed by September 30, 2021; and (12) Provision for authorization of appropriations was made. As a result of the direction provided, the INL and the DOE issued an NGNP Preliminary Project Management

Design option of heat exchanger for the next generation nuclear plant - HTR2008-58175

International Nuclear Information System (INIS)

Oh, C. H.; Kim, E. S.

2008-01-01

The Next Generation Nuclear Plant (NGNP), a very High temperature Gas-Cooled Reactor (VHTR) concept, will provide the first demonstration of a closed-loop Brayton cycle at a commercial scale, producing a few hundred megawatts of power in the form of electricity and hydrogen. The power conversion unit (PCU) for the NGNP will take advantage of the significantly higher reactor outlet temperatures of the VHTRs to provide higher efficiencies than can be achieved with the current generation of light water reactors. Besides demonstrating a system design that can be used directly for subsequent commercial deployment, the NGNP will demonstrate key technology elements that can be used in subsequent advanced power conversion systems for other Generation IV reactors. In anticipation of the design, development and procurement of an advanced power conversion system for the NGNP, the system integration of the NGNP and hydrogen plant was initiated to identify the important design and technology options that must be considered in evaluating the performance of the proposed NGNP. As part of the system integration of the VHTRs and the hydrogen production plant, the intermediate heat exchanger is used to transfer the process heat from VHTRs to the hydrogen plant. Therefore, the design and configuration of the intermediate heat exchanger is very important. This paper will include analysis of one stage versus two stage heat exchanger design configurations and simple stress analyses of a printed circuit heat exchanger (PCHE), helical coil heat exchanger, and shell/tube heat exchanger. (authors)

Role and position of Nuclear Power Plants Research Institute in nuclear power industry

International Nuclear Information System (INIS)

Metke, E.

1984-01-01

The Nuclear Power Plants Research Institute carries out applied and experimental research of the operating states of nuclear power plants, of new methods of surveillance and diagnosis of technical equipment, it prepares training of personnel, carries out tests, engineering and technical consultancy and the research of automated control systems. The main research programme of the Institute is the rationalization of raising the safety and operating reliability of WWER nuclear power plants. The Institute is also concerned with quality assurance of selected equipment of nuclear power plants and assembly works, with radioactive waste disposal and the decommissioning of nuclear power plants as well as with the preparation and implementation of the nuclear power plant start-up. The Research Institute is developing various types of equipment, such as equipment for the decontamination of the primary part of the steam generator, a continuous analyzer of chloride levels in water, a gas monitoring instrument, etc. The prospects are listed of the Research Institute and its cooperation with other CMEA member countries. (M.D.)

Training device for nuclear power plant operators

International Nuclear Information System (INIS)

Schoessow, G. J.

1985-01-01

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

Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant

Energy Technology Data Exchange (ETDEWEB)

Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-09-20

Harvested cables from operating or decommissioned nuclear power plants present an important opportunity to validate models, understanding material aging behavior, and validate characterization techniques. Crystal River Unit 3 Nuclear Generating Plant is a pressurized water reactor that was licensed to operate from 1976 to 2013. Cable segments were harvested and made available to the Light Water Reactor Sustainability research program through the Electric Power Research Institute. Information on the locations and circuits within the reactor from whence the cable segments came, cable construction, sourcing and installation information, and photographs of the cable locations prior to harvesting were provided. The cable variations provided represent six of the ten most common cable insulations in the nuclear industry and experienced service usage for periods from 15 to 42 years. Subsequently, these cables constitute a valuable asset for research to understand aging behavior and measurement of nuclear cables. Received cables harvested from Crystal River Unit 3 Nuclear Generating Plant consist of low voltage, insulated conductor surrounded by jackets in lengths from 24 to 100 feet each. Cable materials will primarily be used to investigate aging under simultaneous thermal and gamma radiation exposure. Each cable insulation and jacket material will be characterized in its as-received condition, including determination of the temperatures associated with endothermic transitions in the material using differential scanning calorimetry and dynamic mechanical analysis. Temperatures for additional thermal exposure aging will be selected following the thermal analysis to avoid transitions in accelerated laboratory aging that do not occur in field conditions. Aging temperatures above thermal transitions may also be targeted to investigate the potential for artifacts in lifetime prediction from rapid accelerated aging. Total gamma doses and dose rates targeted for each material

Status of evaluations and modifications of diesel generator status annunciator systems at various US nuclear power plants

International Nuclear Information System (INIS)

Shindell, B.M.; Rumble, R.P.

1979-10-01

This report documents the current status of evaluations and modifications to the diesel generator status annunciators in a number of US nuclear power plants. These modifications may be required in order to: ensure that all conditions which might render the diesel generators incapable of automatic starting are annunciated in the control room; ensure that the wording on the control room annunciator clearly indicates to the operator that the diesel generator is unavailable if such is the case; and separate disabling and non-disabling annunciation

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

Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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.)

The financing of nuclear power plants

International Nuclear Information System (INIS)

2009-01-01

Many countries have recognised that greater use of nuclear power could play a valuable role in reducing carbon dioxide emissions. However, given the high capital cost and complexity of nuclear power plants, financing their construction often remains a challenge. This is especially true where such financing is left to the private sector in the context of competitive electricity markets. This study examines the financial risks involved in investing in a new nuclear power plant, how these can be mitigated, and how projects can be structured so that residual risks are taken by those best able to manage them. Given that expansion of nuclear power programmes will require strong and sustained government support, the study highlights the role of governments in facilitating and encouraging investment in new nuclear generating capacity

Replacement of major nuclear power plant components for service life extension

International Nuclear Information System (INIS)

Novak, S.

1987-01-01

Problems are discussed associated with replacement of nuclear power plant components with the aim to extend their original scheduled life. The existing foreign experience shows that it is technically feasible to replace practically all basic components for which the necessity of replacement is established. Data is summed up on the replacement of steam generators in US and West German nuclear power plants showing the duration of the job, the total consumption of manhours, the collective dose equivalent and the cost. Attention is also focused on implemented and projected replacements of circulation pipes in nuclear power plants abroad. Based on these figures, the cost is estimated of the replacement of the reactor vessel and the steam generators for WWER-440 nuclear power plants. The conclusion is arrived at that even based on a conservative estimate, the extension by 20 years of the service life of a nuclear power plant is economically more effective than the construction of a new plant. (Z.M.) 2 tabs., 15 refs., 3 figs

East-Asia nuclear/fossil power plant competitiveness

International Nuclear Information System (INIS)

Braun, Ch.

1996-01-01

The competitiveness of a new nuclear plant vs. a new oil or gas fired combined cycle plant or a coal fired plant in East-Asia, is reviewed in the paper. Both the nuclear and the fossil fired plants are evaluated as either utility financed or independent power producer (IPP) financed. Two types of advanced light water reactors (ALWRs) are considered in this paper, namely evolutionary ALWRs (1200 MWe size) and passive ALWRs (600 MWe class). A range of capital and total generation costs for each plant type is reported here. The comparison centers on three elements of overall competitiveness: generation costs, hard currency requirements, and employment requirements. Each of these aspects is considered perspective. Year-by-Year generation cost history over the plant lifetime is shown in some cases. It is found here that a utility financed evolutionary and passive ALWRs are broadly competitive with an IPP financed gas fired combined cycle plant and are more economic than oil fired combined cycle or a coal fired plant. A single unit evolutionary ALWR may have a 12 - 15 % capital cost advantage over a single passive ALWR then adjusted on a per KWe basis. Front-end hard currency requirements of a passive ALWR are 2.5 times higher than for a combined plant and evolutionary ALWRs requires 3.6 times higher up-front cost. However, on a lifetime basis, passive ALWR net hard currency requirements are two times lower than for a combined cycle plant. Evolutionary ALWR net hard currency requirements are three times over than those of a combined cycle plant. The effects of domestic vs. world price of fossil fuels on relative nuclear competitiveness are reviewed in this nuclear competitiveness paper. Employment requirements in an ALWR during both the construction period and lifetime operation, exceed the requirements for oil or gas fired plants by a factor of five. While contributing to overall plant cost, employment requirements can also be viewed as opportunity to increase national

Scientific-technical cooperation with foreign (esp. Europe and INSC partner countries) nuclear regulatory authorities and their technical support organizations in the fields of nuclear safety of operating nuclear power plants and on the concept evaluation of generation 3+ plants. Final report

International Nuclear Information System (INIS)

Wolff, Holger

2016-09-01

The BMUB/BfS-Project 3614I01512 forms the frame of the GRS for the scientific-technical cooperation with Technical Support Organisations and Nuclear Regulatory Authorities in the field of nuclear safety in operating NPPs and for the concept evaluation of generation 3 + plants in Europe and INSC Partner Countries. In the present final project report results are described which were gained within the project duration 15.10.2014 up to the 30.09.2016 in the following working packages: Investigations following the catastrophe of Fukushima Daiichi, Evaluation of selected National Action Plans, DBA and severe accident analyses for NPP with PWR (WWER-440, WWER-1000), cooperation with INSC partner countries on DBA, BDBA and severe accident analyses for WWER plants of generation 3 + and building NRA and safety evaluation capacities and decommissioning of nuclear facilities and disposal of radioactive waste. The results are preceded by an outline on the activities related to the project management and to the planning of the bilateral work.

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

International Nuclear Information System (INIS)

Kato, Seiji

2014-01-01

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

Generation of data base for on-line fatigue life monitoring of Indian nuclear power plant components: Part I - Generation of Green's functions for end fitting

International Nuclear Information System (INIS)

Mukhopadhyay, N.K.; Dutta, B.K.; Kushwaha, H.S.

1994-01-01

Green's function technique is the heart of the on- line fatigue monitoring methodology. The plant transients are converted to stress and temperature response using this technique. To implement this methodology in a nuclear power plant, Green's functions are to be generated in advance. For structures of complex geometries, Green's functions are to be stored in a data base to convert on-line, the plant data to temperature/stress response, using a personal computer. End fitting, end shield, pressurizer, steam generator tube sheet are few such components of PHWR where fatigue monitoring is needed. In the present paper, Green's functions are generated for end fitting of a 235 MWe Indian PHWR using finite element method. End fitting has been analysed using both 3-D and 2-D (axisymmetric) finite element models. Temperature and stress Green's functions are generated at few critical locations using the code ABAQUS. (author). 10 refs., 11 figs

Preinspection of nuclear power plant systems

International Nuclear Information System (INIS)

1975-01-01

The general plans of the systems affecting the safety of the nuclear power plants are accepted by the Institute of Radiation Protection (IRP) on the basis of the preinspection of the systems. This is the prerequisite of the preinspection of the structures and components belonging to these systems. Exceptionally, when separately agreed, the IRP may perform the preinspection of a separate structure or component, although the preinspection documentation of the whole system, e.g. the nuclear heat generating system, has not been accepted. This guide applies to the nuclear power plant systems that have been defined to be preinspected in the classification document accepted by the IRP

Operator support system for nuclear power plants

International Nuclear Information System (INIS)

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

1987-01-01

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

Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan

Energy Technology Data Exchange (ETDEWEB)

J. K. Wright

2010-09-01

DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Today’s high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760°C. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for

Underwater nuclear power plant structure

International Nuclear Information System (INIS)

Severs, S.; Toll, H.V.

1982-01-01

A structure for an underwater nuclear power generating plant comprising a triangular platform formed of tubular leg and truss members upon which are attached one or more large spherical pressure vessels and one or more small cylindrical auxiliary pressure vessels. (author)

75 FR 44292 - Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of...

Science.gov (United States)

2010-07-28

... and DPR-60] Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2... assessment, and behavioral observation) of the unescorted access authorization program when making the... under consideration to determine whether it met the criteria established in NRC Management Directive (MD...

Operating performance of LWR nuclear generating units

International Nuclear Information System (INIS)

Pia, S.

1984-01-01

This work aims at reviewing, on the basis of historical data, the operational problem areas which explain the degree of availability and productivity achieved up to now by nuclear power plants in commercial operation in the world. The operating performance data of nuclear power plants area analysed with respect to plant type, size and other significant reference parameters and they are evaluated also by comparison with fossil generating unit data. Major performance indices data are presented for both nuclear and fossil units type and distribution of outage causes. Unplanned full outages caused by nuclear power plant equipment and components failure are particulary emphasized. The trend for unplanned full outages due to the failure of components shows decreasing numerical values in 1981 with respect to the previous years. But this result should be weighed with the increasing plant unavailability hours needed for maintenance and repair action (chiefly preventive maintenance on critical components). This means that the number and downtime of forced outage must be drastically reduced for economic reasons (production losses and problems associated with the unavailable unit unplanned replacement) as well as for plant safe and reliable operation (sudden unavailability of key components and frequency of transients associated with plant shutdown and routine startup operation)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-03-01

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

Nuclear power generation costs in the United States of America

International Nuclear Information System (INIS)

Willis, W.F.

1983-01-01

Increasing world energy prices and shortages of fuel resources make the utilization of nuclear power extremely important. The United States nuclear power industry represents the largest body of nuclear power experience in the world. Analysis of the recent United States experience of substantial increases in the cost of nuclear power generation provides good insight into the interdependence of technological, financial, and institutional influences and their combined impact on the economic viability of nuclear power generation. The various factors influencing ultimate generation costs, including construction cost, fuel cost, regulatory reviews, and siting considerations are discussed, and their relative impacts are explored, including discussion of design complexity and related regulatory response. A closer look into the recent relatively high escalation of nuclear plant construction costs shows how differing economic conditions can affect the relative cost effectiveness of various methods of power generation. The vulnerability of capital-intensive, long-lead-time projects to changes in economic conditions and uncertainty in future power demands is discussed. Likewise, the pitfalls of new designs and increased sophistication are contrasted to the advantages which result from proven designs, reliable engineering, and shorter lead times. The value of reliable architect-engineers experienced in the design and construction of the plant is discussed. A discussion is presented of additional regulatory requirements stemming from public safety aspects of nuclear power. These include recognition of requirements for the very large effort for quality assurance of materials and workmanship during plant construction and operation. Likewise, a discussion is included of the demanding nature of operations, maintenance, and modification of plants during the operational phase because of the need for highly qualified operations and maintenance personnel and strict quality assurance

Development of new nuclear power plants in the Republic of Korea. Annex 4

International Nuclear Information System (INIS)

Kim, Jung-Cha; Park, Kee-Cheol

2002-01-01

Nuclear power in Korea is one of our major energy sources, which accounting for approximately 50 % of the total share of electric generation using the safest and most stable methods. Based on the outstanding performance of nuclear power generation, Korea plans to construct eight (8) new nuclear power plants to maintain nuclear power as a major contributor to the national energy mix by 2014. In order to ensure that nuclear power plants are safer and more economical than any conventional electric power sources, KEPCO has developed the improved Korea Standard Nuclear Power Plant (KSNP + ) and the Korea Next Generation Reactor (KNGR) by utilizing over 30 years of expertise and learned technologies gained from construction, design, operation of sixteen nuclear units. Recently, KEPCO has developed its own project management tool, the Nuclear Project Control System (NPCS), which integrates schedule, material, cost, drawing and documentation into a computerized system, to be utilized for construction of the nuclear power plants. This paper summarizes KEPCO's various efforts for design improvement of KSNP + and KNGR in terms of performance and economic viability for construction of new nuclear power plants in Korea. (author)

A reliability program for emergency diesel generators at nuclear power plants: Maintenance, surveillance, and condition monitoring

International Nuclear Information System (INIS)

Lofgren, E.V.; Henderson, W.; Burghardt, D.; Kripps, L.; Rothleder, B.

1988-12-01

This report is a companion report on NUREG/CR-5078, Volume 1, ''A Reliability Program for Emergency Diesel Generators at Nuclear Power Plants: Program Structure.'' The purpose of this report is to provide technical findings and insights related to: failure evaluation, troubleshooting, maintenance, surveillance, and condition monitoring. Examples and recommendations are provided for each of these areas based on actual emergency diesel generator (EDG) operating experience and the opinions of diesel generator experts. This report expands the more general guidance provided in Volume 1. In addition, a discussion of EDG interactions with other plant systems (e.g., instrument, air, service water, dc power) is provided since experience has shown that these support systems and their operation can adversely affect EDG reliability. Portions of this report have been designed for use by onsite personnel for evaluating operational characteristics of EDGs. 5 refs., 8 figs., 7 tabs

The third generation of nuclear power development

International Nuclear Information System (INIS)

Townsend, H.D.

1987-01-01

Developing nations use the nuclear plant option to satisfy important overall national development objectives, in addition to providing economical electric power. The relative importance of these two objectives changes as the nuclear program develops and the interim milestones are reached. This paper describes the three typical stages of nuclear power development programs. The first and the second generations are development phases with the third generation reaching self sufficiency. Examples are presented of European and Far East countries or regions which have reached of are about to step into the third generation phase of development. The paper concludes that to achieve the objective of a nuclear power self sufficiency, other than merely filling the need of economical electric power, a careful technology transfer plan must be followed which sets realistic and achievable goals and establishes the country as a reliable and technically competent member of the nuclear power industry. (author)

Maintenance of nuclear power plants

International Nuclear Information System (INIS)

Lashgari, Farbod.

1995-01-01

This paper is about maintenance of nuclear power plants. In part one, the outage management of nuclear power plants has described. Meaning of the outage and objectives of outage management is given in introduction. The necessity of a long-term outage strategy is shown in chapter one. The main parts of an outage are as follows: Planning; Preparation; Execution, Each of them and also post-outage review have been explained in the followed chapters. Part two deals with technical details of main primary components of nuclear power plant type WWER. After an introduction about WWER reactors, in each chapter first the general and detailed description of main primary components has given and then their maintenance schedules and procedures. Chapter about reactor and steam generator is related to both types of WWER-440 and WWER-1000, but chapter about reactor coolant pump has specified to WWER-1000 to be more in details.(author)

Dose reduction at nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.; Dionne, B.J.

1983-01-01

The collective dose equivalent at nuclear power plants increased from 1250 rem in 1969 to nearly 54,000 rem in 1980. This rise is attributable primarily to an increase in nuclear generated power from 1289 MW-y to 29,155 MW-y; and secondly, to increased average plant age. However, considerable variation in exposure occurs from plant to plant depending on plant type, refueling, maintenance, etc. In order to understand the factors influencing these differences, an investigation was initiated to study dose-reduction techniques and effectiveness of as low as reasonably achievable (ALARA) planning at light water plants. Objectives are to: identify high-dose maintenance tasks and related dose-reduction techniques; investigate utilization of high-reliability, low-maintenance equipment; recommend improved radioactive waste handling equipment and procedures; examine incentives for dose reduction; and compile an ALARA handbook

New nuclear power plants in Europe 1984. Pt 2

International Nuclear Information System (INIS)

Anon.

1984-01-01

The atw report on new nuclear power plants in Europe contains both a survey of the Federal Republic of Germany, which was pubslished in the April 1984 issue, and an overview of the nuclear power plant situation in 26 European countries including the Soviet Union and six other CMEA countries. Also this year's review includes specific status reports, complete with technical information, about all nuclear generating units under construction, in the project and concrete planning phases. The fifteen nuclear power plants newly commissioned in Europe since last year's atw report was published are covered in a similar way. Moreover, introductory summaries describe the plants in operation in each country and their 1983 electricity generation. A general introduction provides an outlook on developments in Western and Eastern Europe. The total number of nuclear power plants now in operation and under construction in Europe is 300 units with an aggregate gross 219, 320 MWe. Of these, 185 units are located in Western Europe, 115 in Eastern Europe. The units currently in operation of this total are 180 with 103,978 MWe in sixteen European countries; of these, 126 units with 74,869 MWe are run in eleven West European countries, 54 units with an aggregate 29,109 MWe in five East European countries. Of the 120 nuclear generating units at present under construction with an aggregate 115,342 MWe in fifteen European countries, 59 units with 63,442 MWe are located in eight West European, 61 units with 51,900 MWe in seven East European countries. (orig./UA) [de

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

International Nuclear Information System (INIS)

Srivastava, Gaurava Deep; Kulkarni, R.D.

2015-01-01

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

Modernization of turbines in nuclear power plants

International Nuclear Information System (INIS)

Harig, T.

2005-01-01

An ongoing goal in the power generation industry is to maximize the output of currently installed assets. This is most important at nuclear power plants due to the large capital investments that went into these plants and their base loaded service demands. Recent trends in the United States show a majority of nuclear plants are either obtaining, or are in the process of obtaining NRC approvals for operating license extensions and power uprates. This trend is evident in other countries as well. For example, all Swedish nuclear power plants are currently working on projects to extend their service life and maximize capacity through thermal uprate and turbine-generator upgrade with newest technology. The replacement of key components with improved ones is a means of optimizing the service life and availability of power plants. Economic advantages result from increased efficiency, higher output, shorter startup and shutdown times as well as reduced outage times and service costs. The rapid advances over recent years in the development of calculation programs enables adaptation of the latest blading technology to the special requirements imposed by steam turbine upgrading. This results in significant potential for generating additional output with the implementation of new technology, even without increased thermal power. In contrast to maintenance and investment in pure replacement or repair of a component with the primary goal of maintaining operability and reliability, the additional output gained by upgrading enables a return on investment to be reaped. (orig.)

Energy Balance of Nuclear Power Generation. Life Cycle Analyses of Nuclear Power

International Nuclear Information System (INIS)

Wallner, A.; Wenisch, A.; Baumann, M.; Renner, S.

2011-01-01

The accident at the Japanese nuclear power plant Fukushima in March 2011 triggered a debate about phasing out nuclear energy and the safety of nuclear power plants. Several states are preparing to end nuclear power generation. At the same time the operational life time of many nuclear power plants is reaching its end. Governments and utilities now need to take a decision to replace old nuclear power plants or to use other energy sources. In particular the requirement of reducing greenhouse gas emissions (GHG) is used as an argument for a higher share of nuclear energy. To assess the contribution of nuclear power to climate protection, the complete life cycle needs to be taken into account. Some process steps are connected to high CO2 emissions due to the energy used. While the processes before and after conventional fossil-fuel power stations can contribute up to 25% of direct GHG emission, it is up to 90 % for nuclear power (Weisser 2007). This report aims to produce information about the energy balance of nuclear energy production during its life cycle. The following key issues were examined: How will the forecasted decreasing uranium ore grades influence energy intensity and greenhouse emissions and from which ore grade on will no energy be gained anymore? In which range can nuclear energy deliver excess energy and how high are greenhouse gas emissions? Which factors including ore grade have the strongest impact on excess energy? (author)

Power generation costs. Coal - nuclear power

International Nuclear Information System (INIS)

1979-01-01

This supplement volume contains 17 separate chapters investigating the parameters which determine power generation costs on the basis of coal and nuclear power and a comparison of these. A detailed calculation model is given. The complex nature of this type of cost comparison is shown by a review of selected parameter constellation for coal-fired and nuclear power plants. The most favourable method of power generation can only be determined if all parameters are viewed together. One quite important parameter is the load factor, or rather the hours of operation. (UA) 891 UA/UA 892 AMO [de

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)

Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Garcia V, M.A.; Hernandez M, I.A.; Martin del Campo M, C.

2004-01-01

The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

Nuclear power plant construction activity, 1986

International Nuclear Information System (INIS)

1987-01-01

Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors

Projected role of nuclear power in Egypt and problems encountered in implementing the first nuclear power plant

International Nuclear Information System (INIS)

Effat, K.E.A.; Sirry, H.; El-Sharkawy, E.

1977-01-01

The increasing rise in fossil-fuel prices has favourably affected the economics of nuclear power generation bringing down the economically competitive size of nuclear units closer to small sizes compatible with grid capacities in developing countries. This encouraged Egypt to turn to nuclear power to fulfil its future power needs. In implementing its first nuclear power plant, Egypt is facing various problems. The capacity of the national electric power system and its inherent characteristics pose certain restrictions on the size and design of the nuclear plant required. The availability of sufficient local qualified management, engineering and technical personnel to participate in both precontractual and construction phases of the plant is quite a major problem. Lack of local developed industry to back up the construction phase implies the dependence to a large extent on imported equipment, materials and technology. The paper reviews the present and projected power demands in Egypt and the factors behind the decision to introduce a nuclear power generation programme. Various problems encountered and anticipated in introducing the first nuclear power plant are also discussed. (author)

Safety in Swiss nuclear power plants

International Nuclear Information System (INIS)

Cederqvist, H.

1992-01-01

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

New reactor concepts for new generation of nuclear power plants: an overview, invited paper

International Nuclear Information System (INIS)

Vujic, J.; Greenspan, E.; Milosevic, M.

2006-01-01

The outlook for energy demand underscores the need to increase the share of nuclear energy production. Achieving the vision of sustainable growth of nuclear energy will require development of both advanced nuclear fuel cycles and next generation reactor technologies and advanced reprocessing and fuel treatment technologies. To achieve this vision, the US department of energy (DOE) has adopted new strategy, the Global Nuclear Energy Partnership (GNEP), which integrates earlier programs: the Generation IV Nuclear Energy Systems Initiative (Generation IV), Nuclear Hydrogen Initiative (NHI), and the Advanced Fuel Cycle Initiative (AFCI) with proliferation-resistant spent fuel reprocessing to minimize nuclear waste. Generation IV furthers this vision beyond previous energy systems, such as Generation III+, through incremental improvements in economic competitiveness, sustainability, development of passively safe systems, and breakthrough methods to reduce the routes of nuclear proliferation. This paper summarizes the main characteristics of the six most promising nuclear energy systems identified by the Generation IV Roadmap and reviews some Generation IV system designs for small-side proliferation resistant reactors being developed by University of California at Berkeley. (author)

Affective imagery and acceptance of replacing nuclear power plants.

Science.gov (United States)

Keller, Carmen; Visschers, Vivianne; Siegrist, Michael

2012-03-01

This study examined the relationship between the content of spontaneous associations with nuclear power plants and the acceptance of using new-generation nuclear power plants to replace old ones. The study also considered gender as a variable. A representative sample of the German- and French-speaking population of Switzerland (N= 1,221) was used. Log-linear models revealed significant two-way interactions between the association content and acceptance, association content and gender, and gender and acceptance. Correspondence analysis revealed that participants who were opposed to nuclear power plants mainly associated nuclear power plants with risk, negative feelings, accidents, radioactivity, waste disposal, military use, and negative consequences for health and environment; whereas participants favoring nuclear power plants mainly associated them with energy, appearance descriptions of nuclear power plants, and necessity. Thus, individuals opposing nuclear power plants had both more concrete and more diverse associations with them than people who were in favor of nuclear power plants. In addition, participants who were undecided often mentioned similar associations to those participants who were in favor. Males more often expressed associations with energy, waste disposal, and negative health effects. Females more often made associations with appearance descriptions, negative feelings, and negative environmental effects. The results further suggest that acceptance of replacing nuclear power plants was higher in the German-speaking part of the country, where all of the Swiss nuclear power plants are physically located. Practical implications for risk communication are discussed. © 2011 Society for Risk Analysis.

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Recycling of concrete waste generated from nuclear power plant dismantling

International Nuclear Information System (INIS)

Ogawa, Hideo; Nagase, Takahiro; Tanaka, Hiroaki; Nawa, Toyoharu

2012-01-01

Non-radioactive concrete waste generated from dismantling of a standard large nuclear power plant is estimated to be about 500,000 tons in weight. Using such waste as recycled aggregate within the enclosure of the plant requires a new manufacturing technology that generates a minimal amount of by-product powder. Recycled aggregate has brittle parts with defects such as cracks, pores, and voids in residual paste from original concrete. This study presents a method of selectively removing the defective parts during manufacture to improve the quality of the recycled fine aggregate. With this selective removal method used, the amount of by-product powder can be reduced by half as compared to that by a conventional method. The influences of the characteristics of the recycled fine aggregate on the flowability and strength of the mortar using recycled fine aggregate were evaluated by multiple linear regression analysis. The results clearly showed that the flowability was primarily affected by the filling fraction of recycled fine aggregate, while the compressive strength of mortar was primarily affected by the fraction of defects in the aggregate. It was also found that grains produced by a granulator have more irregularities in the surfaces than those produced by a ball mill, providing an increased mortar strength. Using these findings from this study, efforts are also being made to develop a mechanical technology that enables simultaneous processing of decontamination and recycling. The granulator under consideration is capable of grinding the surfaces of irregularly shaped particles and may be used successfully, under optimal conditions, for the surface decontamination of concrete waste contaminated with radioactive materials. (author)

Use of self-organizing maps for classification of defects in the tubes from the steam generator of nuclear power plants

International Nuclear Information System (INIS)

Mesquita, Roberto Navarro de

2002-01-01

This thesis obtains a new classification method for different steam generator tube defects in nuclear power plants using Eddy Current Test signals. The method uses self-organizing maps to compare different signal characteristics efficiency to identify and classify these defects. A multiple inference system is proposed which composes the different extracted characteristic trained maps classification to infer the final defect type. The feature extraction methods used are the Wavelet zero-crossings representation, the linear predictive coding (LPC), and other basic signal representations on time like module and phase. Many characteristic vectors are obtained with combinations of these extracted characteristics. These vectors are tested to classify the defects and the best ones are applied to the multiple inference system. A systematic study of pre-processing, calibration and analysis methods for the steam generator tube defect signals in nuclear power plants is done. The method efficiency is demonstrated and characteristic maps with the main prototypes are obtained for each steam generator tube defect type. (author)

Diesel-generator reliability at nuclear power plants: data and preliminary analysis. Interim report

International Nuclear Information System (INIS)

McClymont, A.; McLagan, G.

1982-06-01

This report summarizes work performed under RP1233-1 relating to the collection and analysis of data pertaining to diesel generator reliability in nuclear power plants. Drawing from data collected on-site at plants, data supplied by utilites, and data from Licensee Event Reports (LERs), the report describes methods of deriving reliability estimates from data for use in probabilistic risk assessment and presents results when these methods are applied to data collected from 14 plants. Specifically, data are used to estimate diesel failure probabilities for failures to start and failure rates for failures to continue to run. A sampling theory approach and a Bayesian approach to failure probability estimation are compared. The data are used to derive estimates of diesel repair time for some plants, maintenance outages, and multiple diesel failure rates. In addition, a section is included that presents suggestions for failure-rate estimation when an accurate count of diesel start attempts at a plant is not available. The final section presents an analysis of diesel failures based on data from LERs, including a breakdown of failure event by subsystem, failure mode, and failure cause. Appendixes include detailed summaries of the data used in the analysis of previous sections

Generation of floor spectra compatible time histories for equipment seismic qualification in nuclear power plants

International Nuclear Information System (INIS)

Shyu, Y.-S.; Luh, Gary G.; Blum, Arie

2004-01-01

This paper proposes a procedure for generating floor response spectra compatible time histories used for equipment seismic qualification in nuclear power plants. From the 84th percentile power spectrum density function of an earthquake ensemble of four randomly generated time history motions, a statistically equivalent time history can be obtained by converting the power spectrum density function from the frequency domain into the time domain. With minor modification, if needed, the converted time history will satisfy both the spectral and the power spectrum density enveloping criteria, as required by the USNRC per Revision 2 of the Standard Review Plan, Section 3.7.1. Step-by-step generating procedures and two numerical examples are presented to illustrate the applications of the methodology. (author)

Nuclear Energy In Switzerland: It's going ahead. Challenges For The Swiss Nuclear Society Young Generation Group

Energy Technology Data Exchange (ETDEWEB)

Streit, Marco [Aare-Tessin Ltd for Electricity, Bahnhofquai 12, CH-4601 Olten (Switzerland); Bichsel, Thomas [BKW FMB Energie AG, NPP Muehleberg, CH-3203 Muehleberg (Switzerland); Fassbender, Andre [NPP Goesgen-Daeniken AG, CH-4658 Daeniken (Switzerland); Horvath, Matthias [National Emergency Operations Centre, CH-8044 Zurich (Switzerland)

2008-07-01

Swiss energy policy is focused on generating domestic electric power without combusting fossil fuels for already four decades. Roughly 60% of the electricity is generated in hydroelectric plants, which is possible due to the country's favourable topography; the remaining 40% are produced by the country's five nuclear power plants (NPPs). As in any other country nuclear power has its enemies in Switzerland. Due to the direct democracy system in Switzerland the nuclear opposition has a lot of possibilities to disturb the energy policy. Since 1969, when the first Swiss nuclear power plant went online, four plebiscites were held on the issue of civil use of nuclear energy. Four times Swiss citizens voted in favour of further operation of the existing plants also in the latest battle for nuclear energy, which was won in 2003. In 2005 and 2006 several Swiss studies about the future energy situation, especially the electricity situation, have been published. All off them show clearly that there will be a big gab around the year 2020 when the oldest three nuclear power plants will fade out. A public debate was started, how to solve the problem. Beside others, building new nuclear power plants was mentioned and discussed rationally. In 2007 the energy police of the Swiss government changed into a more nuclear friendly position and at the end of the same year some electricity companies lunched a new build program. Hosting the International Youth Nuclear Congress 2008 (IYNC 2008) in Switzerland seems to be just the right moment for the nuclear industry in our country. The slightly changed surroundings effected the organization of Swiss Nuclear Society (SNS) and SNS Young Generation Group (SNSYG) and enlarged the fields of activities for SNSYG. Those activities mentioned in the previous chapters will be developed in the future. The discussion about new builds in Switzerland has started and because of that more nuclear activities in Switzerland will occur. And surely

Nuclear power generation and automation technology

International Nuclear Information System (INIS)

Korei, Yoshiro

1985-01-01

The proportion of nuclear power in the total generated electric power has been increasing year after year, and the ensuring of its stable supply has been demanded. For the further development of nuclear power generation, the heightening of economical efficiency which is the largest merit of nuclear power and the public acceptance as a safe and stable electric power source are the important subjects. In order to solve these subjects, in nuclear power generation, various automation techniques have been applied for the purpose of the heightening of reliability, labor saving and the reduction of radiation exposure. Meeting the high needs of automation, the automation technology aided by computers have been applied to the design, manufacture and construction, operation and maintenance of nuclear power plants. Computer-aided design and the examples of design of a reactor building, pipings and a fuel assembly, an automatic welder for pipings of all position TIG welding type, a new central monitoring and control system, an automatic exchanger of control rod-driving mechanism, an automatic in-service inspection system for nozzles and pipings, and a robot for steam generator maintenance are shown. The trend of technical development and an intelligent moving robot, a system maintenance robot and a four legs walking robot are explained. (Kako, I.)

Economic analysis of nuclear power generation

International Nuclear Information System (INIS)

Lee, Young Gun; Lee, Han Myung; Song, Ki Dong; Lee, Man Ki; Kim, Seung Su; Moon, Kee Hwan; Chung, Whan Sam; Kim, Kyung Pyo; Cho, Sang Goo

1992-01-01

The purpose of this study is to clarify the role of nuclear power generation under the circumstances of growing concerns about environmental impact and to help decision making in electricity sector. In this study, efforts are made to estimate electricity power generation cost of major power options by incorporating additional cost to reduce environmental impact and to suggest an optimal plant mix in this case. (Author)

Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

International Nuclear Information System (INIS)

1986-12-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

Study on economic potential of nuclear-gas combined cycle power generation in Chinese market

International Nuclear Information System (INIS)

Zhou Zhiwei; Bian Zhiqiang; Yang Mengjia

2004-01-01

Facing the challenges of separation of electric power plant and grid, and the deregulation of Chinese electricity supplying market in near future, nuclear power plants mainly operated as based load at the present regulated market should look for new operation mode. The economics of electric generation with nuclear-natural gas combined cycle is studied based on current conditions of natural gas and nuclear power plants in China. The results indicate that the technology development of nuclear-natural gas combined cycle for power generation is of potential prospects in Chinese electric market. (authors)

Lessons learned from first generation nuclear plant probabalistic risk assessments

International Nuclear Information System (INIS)

Garrick, B.J.

1984-01-01

The paper by Garrick summarizes the state-of-the-art in what are perhaps the most archetypical probabilistic risk assessments (PRAs). Because of its unique regulatory environment and because of the high levels of perceived (not necessarily actual) risk, the nuclear industry more than any other has been concerned with quantitative risk analysis. Garrick's paper summarizes the lessons learned from ten PRA's conducted in the nuclear industry, including six that can be characterized as full-scope risk studies. Most of the quantitative data, though, came from two especially thorough studies done for the Zion and Indian Point power plants, operated by Commonwealth Edison and Consolidated Edison respectively. The principal conclusions of the Garrick survey are that the public risk (from radiation release) is now known to be very small for commercial nuclear power plants, but that the risk to utilities (from core damage) is somewhat larger. Significant radiation releases require both core meltdown -- an event occurring only about once every 10,000 reactor-years -- and containment failure, occurring only about once in every hundred meltdowns

Reduction of capital costs of nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The competitiveness of nuclear power plants depends largely on their capital costs represent some 60 per cent of their total generation costs. Reviewing and analysing ways and means to reduce capital costs of nuclear power plants are essential to enhance the economic viability of the nuclear option. The report is based upon cost information and data provided by experts from NEA Member countries. It investigates the efficiency of alternative methods for reducing capital costs of nuclear units. It will provide stakeholders from the industry and governmental agencies with relevant elements in support of policy making. (author)

Manpower development for safe operation of nuclear power plant. China. Steam generator maintenance, cleaning and repair. Activity: 3.1.8-Task-04. Technical report

International Nuclear Information System (INIS)

Esposito, J.N.

1994-01-01

The objective of this mission was to present detailed state-of-the-art information on steam generator design, operations and maintenance, to the management, engineers and operators of the Qinshan Nuclear Power Plants. In addition, some limited operation was presented by the Qinshan Nuclear Power Plant representatives in order to aid in focussing the presentations and promoting a high level of discussion

Economic analysis of nuclear power plant for decision making in Thailand

International Nuclear Information System (INIS)

Siri-Udomrat, Thawee

2002-01-01

According to National Economic and Social Development's forecast, electricity demand in Thailand from now up to the year 2011 will rise more than 147 %. So, the Eighth-Ninth National Economic and Social Development Plans (NESDP) (1997-2006) has launched the main energy resources, imported oil, coal, imported coal, natural gas and hydro. From the Tenth NESDP up (2007-) may launch the energy option more, such as liquid natural gas and nuclear. Although Thailand has reserved lignite and natural gas enough for more than two centuries, we have found that the energy resources are inadequate and expected to be imported for over 60%. So nuclear energy is necessary and suitable for alternative source of energy. The main factors used for power generating cost calculation of nuclear power plant are capital investment cost, nuclear fuel cycle cost, operation and maintenance cost, and infrastructure cost. Consequently, the parameter which indicating the performance of power plant and power generation cost are load factor, net power rating, and economic life. Another variable group are interest rate, escalation rate, and discount rate. The overhead and operation cost are always changed due to the economic or other variants of interest rate, and out of schedule operation or the changing of fuel cost. In order to compare each type of power plant, we had to use present worth value analytical technique to calculate the the levelized energy cost (mills/kWh) by giving present worth value of average power generation cost equal to present worth value of total cost of the project and operation of power plant. The economic parameter will affect exchange rate and discount rate calculation. To assess the economic analysis of cost and cost benefit of Electricity Generating Authority of Thailand (EGAT) project, real interest rate for discount rate (social discount rate) will be calculated. By the year 1992-1998, the social discount rate of Thailand is estimated at about 7.59%. For studying

FEATURES OF ELECTRIC MOTOR CHOICE FOR NUCLEAR POWER PLANT TECHNOLOGICAL OBJECTS

Directory of Open Access Journals (Sweden)

V.V. Shevchenko

2013-06-01

Full Text Available Nuclear power plants remain the basic power generating enterprises for Ukraine. Execution of works on their reliability control and operating conditions optimization is therefore of current importance. Trouble-free nuclear power plant operation is a vital technical, economical, and ecological problem, a solution to which is largely specified by reliable operation of electric equipment, namely, electric motors of nuclear power plant technological process drives.

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.

The economics of coal and nuclear power plants

International Nuclear Information System (INIS)

Prior, M.J.

1978-01-01

This paper is largely based on a comparison of electrical generating costs from coal-fired power plants and thermal nuclear reactors. Following an introductory section, the subject is considered under the following headings: methodology; cost basis (capital costs, fuel costs, plant factors); generating costs; the fast breeder reactor -general issues; the economics of fast breeder reactors; conclusions and questions. (U.K.)

Nuclear dual-purpose plants for industrial energy

International Nuclear Information System (INIS)

Klepper, O.H.

1976-01-01

One of the major obstacles to extensive application of nuclear power to industrial heat is the difference between the relatively small energy requirements of individual industrial plants and the large thermal capacity of current power reactors. A practical way of overcoming this obstacle would be to operate a centrally located dual-purpose power plant that would furnish process steam to a cluster of industrial plants, in addition to generating electrical power. The present study indicates that even relatively remote industrial plants could be served by the power plant, since it might be possible to convey steam economically as much as ten miles or more. A survey of five major industries indicates a major potential market for industrial steam from large nuclear power stations

Insurance risk of nuclear power plant concentrations

International Nuclear Information System (INIS)

Feldmann, J.

1976-01-01

The limited number of sites available in the Federal Republic of Germany for the erection of nuclear power plants has resulted in the construction of multiple nuclear generating units on a few sites, such as Biblis, Gundremmingen and Neckarwestheim. At a value invested of approximately DM 1,200/kW this corresponds to a property concentration on one site worth DM 2 - 3 billion and more. This raises the question whether a concentration of value of this magnitude does not already exceed the limits of bearable economic risks. The property risk of a nuclear power plant, as that of any other industrial plant, is a function of the property that can be destroyed in a maximum probable loss. Insurance companies subdivide plants into so-called complex areas in which fire damage or nuclear damage could spread. While in some foreign countries twin nuclear power plants are built, where the technical systems of both units are installed in one building without any physical separation, dual unit plants are built in the Federal Republic in which the complexes with a high concentration of valuable property are physically separate building units. As a result of this separation, property insurance companies have no grounds for assessing the risk and hence, the premium different from those of single unit plants. (orig.) [de

Low-temperature nuclear heat applications: Nuclear power plants for district heating

International Nuclear Information System (INIS)

1987-08-01

The IAEA reflected the needs of its Member States for the exchange of information in the field of nuclear heat application already in the late 1970s. In the early 1980s, some Member States showed their interest in the use of heat from electricity producing nuclear power plants and in the development of nuclear heating plants. Accordingly, a technical committee meeting with a workshop was organized in 1983 to review the status of nuclear heat application which confirmed both the progress made in this field and the renewed interest of Member States in an active exchange of information about this subject. In 1985 an Advisory Group summarized the Potential of Low-Temperature Nuclear Heat Application; the relevant Technical Document reviewing the situation in the IAEA's Member States was issued in 1986 (IAEA-TECDOC-397). Programme plans were made for 1986-88 and the IAEA was asked to promote the exchange of information, with specific emphasis on the design criteria, operating experience, safety requirements and specifications for heat-only reactors, co-generation plants and power plants adapted for heat application. Because of a growing interest of the IAEA's Member States about nuclear heat employment in the district heating domaine, an Advisory Group meeting was organized by the IAEA on ''Low-Temperature Nuclear Heat Application: Nuclear Power Plants for District Heating'' in Prague, Czechoslovakia in June 1986. The information gained up to 1986 and discussed during this meeting is embodied in the present Technical Document. 22 figs, 11 tabs

Nuclear power plants in the world as of June 30, 1982

International Nuclear Information System (INIS)

1982-01-01

In this list of nuclear power plants, the result is summarized when Japan Atomic Industrial Forum, Inc., performed the survey of the nuclear power plants in operation, under construction, ordered and at planning stage in the world, which is the first survey of twice a year. The nuclear power plants in operation in the world were 267, amounting to the total capacity of more than 168 million kWe, those under construction were 243 and more than 232 million kWe, those ordered were 32 and more than 31 million kWe, and those at the planning stage were 137 and more than 138 million kWe. The total was 679 and more than 570 million kWe. In this half year, 3 plants with 2651 MWe capacity started operation, while two shut down plants were removed from the list. The People's Republic of China was added, but Norway was removed, accordingly 41 countries engaged in nuclear power generation. Due to the stagnation of world economy and the relaxation in the demand and supply of petroleum, the future progress of nuclear power generation is uncertain. In light water reactors, the trend toward PWRs in future is observed. FBRs are still slight but tend to increase. The situation of nuclear power generation in Japan and main foreign countries is reported. (Kako, I.)

Nuclear power plant

International Nuclear Information System (INIS)

Schabert, H.P.

1976-01-01

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

Seismic analysis of nuclear power plants

International Nuclear Information System (INIS)

Halbritter, A.L.

1984-01-01

Nuclear Power Plants require exceptional safety guarantees which are reflected in a rigorous control of the employed materials, advanced construction technology, sophisticated methods of analysis and consideration of non conventional load cases such as the earthquake loading. In this paper, the current procedures used in the seismic analysis of Nuclear Power Plants are presented. The seismic analysis of the structures has two objectives: the determination of forces in the structure in order to design it against earthquakes and the generation of floor response spectra to be used in the design of mechanical and electrical components and piping systems. (Author) [pt

I and C upgrading at nuclear power plants

International Nuclear Information System (INIS)

Tamiri, A.

2003-01-01

Continuing the operation of existing nuclear power plants will help reduce the number of new base-load nuclear and fossil power plants that need to be built. Old nuclear power plants in Canada are operating with analog instrumentation and control systems. For a number of reasons, such as changes and improvements in the applicable standards and design, maintenance problems due to the lack of spares, technical obsolescence, the need to increase power production, availability, reliability and safety, and in order to reduce operation and maintenance costs, instrumentation and control upgrading at nuclear power plants in a cost effective manner should be considered the greatest priority. Failures of instrumentation and control (I and C) due to aging and obsolescence issues may have an immediate negative impact on plant reliability and availability and also affect long-term plant performance and safety. In today's competitive marketplace, power plants are under pressure to cut spending on maintenance while reducing the risk of equipment failure that could cause unplanned outage. To improve plant safety and availability, old nuclear power plants will require investment in new technologies that can improve the performance and reduce the costs of generation by addressing the long term reliability of systems by up-grading to modem digital instrumentation and control and optimization opportunities. Boiler drum level control at nuclear power plants is critical for both plant protection and equipment safety and applies equality to high and low levels of water within the boiler drum. Plant outage studies at Pickering Nuclear have identified boiler drum level control and feed water control systems as major contributors to plant unavailability. Ways to improve transient and steady state response, upgrading existing poor analog control systems for boiler level and feed-water control systems at Pickering Nuclear, with enhanced and robust controller will be discussed in this paper

Plant-specific evaluations of Transamerica Delaval diesel engines for nuclear service

International Nuclear Information System (INIS)

Dingee, D.A.; Laity, W.W.; Nesbitt, J.F.

1985-03-01

This paper discusses the approach taken to evlauate the readiness of Transamerica Delaval, Inc. (TDI) diesel generators for nuclear service at five power plants: Catawba, Comanche Peak, Grand Gulf, San Onofre, and Shoreham. TDI engines in these and other nuclear power plants have been the subject of a coordinated effort by 13 nuclear utilities to address reliability and quality issues. The utilities formed the TDI Diesel Generator Owners' Group and prepared a comprehensive plan for requalifying the engines as emergency power sources. Prior to full implementation of the plan by the Owners' Group and final review of the findings by the US Nuclear Regulatory Commission, several member plants became candidates for operating licenses. The TDI engines in those plants, including the five listed above, were evaluated on a case-by-case basis, taking into consideration the factors discussed in this paper. 2 refs

Nuclear power plant outage optimisation strategy

International Nuclear Information System (INIS)

2002-10-01

Competitive environment for electricity generation has significant implications for nuclear power plant operations, including among others the need of efficient use of resources, effective management of plant activities such as on-line maintenance and outages. Nuclear power plant outage management is a key factor for good, safe and economic nuclear power plant performance which involves many aspects: plant policy, co-ordination of available resources, nuclear safety, regulatory and technical requirements and, all activities and work hazards, before and during the outage. This technical publication aims to communicate these practices in a way they can be used by operators and utilities in the Member States of the IAEA. It intends to give guidance to outage managers, operating staff and to the local industry on planning aspects, as well as examples and strategies experienced from current plants in operation on the optimization of outage period. This report discusses the plant outage strategy and how this strategy is actually implemented. The main areas identified as most important for outage optimization by the utilities and government organizations participating in this report are: organization and management; outage planning and preparation, outage execution, safety outage review, and counter measures to avoid extension of outages and to easier the work in forced outages. This report was based on discussions and findings by the authors of the annexes and the participants of an Advisory Group Meeting on Determinant Causes for Reducing Outage Duration held in June 1999 in Vienna. The report presents the consensus of these experts regarding best common or individual good practices that can be used at nuclear power plants with the aim to optimize

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

Energy Technology Data Exchange (ETDEWEB)

Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

2007-03-21

In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for

The Cattenom nuclear power plant, at the service of a safe, competitive and CO2-free power generation in the heart of the Lorraine region

International Nuclear Information System (INIS)

2010-01-01

In less than 20 years, Electricite de France (EDF) has built up a competitive park of 58 nuclear power plants, with no equivalent elsewhere, which represents an installed power of 63.1 GW (85% of EDF's power generation). Inside this nuclear park, the national power generation centre of Cattenom comprises 4 production units of 1300 MW each (5200 MW as a whole). The facility generated 34 billion kWh in 2009, i.e. 8% of the French national power generation. This brochure presents the life of the power plant under various aspects: power generation, safety priority and culture, maintenance investments, respect of the environment, long-term fuel and wastes management, local economical involvement, transparency and public information, key figures and dates. (J.S.)

The Chinon nuclear power plant, at the service of a safe, competitive and CO2-free power generation in the heart of the Centre region

International Nuclear Information System (INIS)

2010-01-01

In less than 20 years, Electricite de France (EDF) has built up a competitive park of 58 nuclear power plants, with no equivalent elsewhere, which represents an installed power of 63.1 GW (85% of EDF's power generation). Inside this nuclear park, the national power generation centre of Chinon comprises 4 production units of 900 MW each (3600 MW as a whole). The facility generated 19.03 billion kWh in 2009, i.e. 4.8% of the French national power generation. This brochure presents the life of the power plant under various aspects: power generation, safety priority and culture, maintenance investments, respect of the environment, long-term fuel and wastes management, local economical involvement, transparency and public information, key figures and dates. (J.S.)

Aspects related to the decommissioning of the nuclear power plants

International Nuclear Information System (INIS)

Goicea, Andrei; Andrei, Veronica

2003-01-01

All power plants, either coal, gas or nuclear, at the end of their life needs to be decommissioned and demolished and thus, to made the site available for other uses. The first generation nuclear power plants were designed for a life of about 30 years and some of them proved capable of continuing well beyond this term. Newer plants have been designed for a 40 to 60 years operating life. To date, other 90 commercial power reactors have been retired from operation. For nuclear power plants and nuclear facilities in general the decommissioning process consists of some or all of the following activities: the safe management of nuclear materials held in the facility, cleaning-up of radioactivity (decontamination), plant dismantling, progressive demolition of the plant and site remediation. Following the decommissioning, the regulatory controls covering facility end, partially or totally, and the safe site is released for appropriate alternative use. Cernavoda NPP is a young plant and it can benefit from the continuously developing experience of the decommissioning process at the international level. The current experience allows the most metallic parts of a nuclear power to be decontaminated and recycled and makes available proven techniques and equipment to dismantle nuclear facilities safely. As experience is gained, decommissioning costs for nuclear power plants, including disposal of associated wastes, are reducing and thus, contribute in a smaller fraction to the total cost of electricity generation. The new specific Romanian regulations establish a funding system for decommissioning and provisions for long-term radioactive waste management. In the near future a decommissioning plan will be made available for Cernavoda NPP. Since the plant has only 7 years operation, that plan can be improved in order to benefit from international experience that is growing. (authors)

Safety improvements made at the Loviisa nuclear power plant to reduce fire risks originating from the turbine generators

International Nuclear Information System (INIS)

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

1998-01-01

Comprehensive upgrading measures have been completed for the Loviisa Nuclear Power Plant (modified VVER440/V213). These were carried out from the start of the design phase and during operation to ensure safe plant shutdown in the event of a large turbine generator oil fire. These modifications were made mainly on a deterministic basis according to specific risk studies and fire analyses. As part of the probabilistic safety assessment, a fire risk analysis was made that confirmed the importance of these upgrading measures. In fact, they should be considered as design basis modifications for all VVER440 plants. (author)

The trend of the public opinion upon nuclear power generation in internet blog

International Nuclear Information System (INIS)

Maruta, Katsuhiko; Ueda, Yoshitaka

2011-01-01

The authors pay attention to and survey internet information which is called 'blog' to grasp how nuclear power generation information is treated in internet and forms public opinion. Examples of the outcomes are as follows. 1) Numbers of blog reference will change by public opinion upon nuclear power generation. A lot of blog references about nuclear power plants are conducted when a big earthquake occurred. 2) As a feature of the report, numbers of the references against nuclear power generation exceed those which are positive for nuclear power. There are a lot of blog reports which are against nuclear power generation and easy to make readers believe that they are true even if they are based on misunderstanding. It is worried that such reports give people too much negative influence for the public opinion upon nuclear power generation. The authors survey short term trend of the internet public opinion after TEPCO's Fukushima Daiichi Power Plants Accident too. As a result, it is made clear that people's concern upon nuclear power became very high and the ratio of the supporters of nuclear power generation changed after the accident. (author)

Corrective maintenance support system for nuclear power plants

International Nuclear Information System (INIS)

Kakiuchi, Tetsuo

1996-01-01

With increase of share of nuclear power generation in electric power supply in Japan, requirement for further safe operation and improvement of economics for the nuclear power plants is promoting. The pressed water type (PWR) nuclear power plant in operation in Japan reaches to 22 sets, application rate of the instruments is 74% as mean value for 7 years since 1989 and in high level, which is due to a result of preventive maintenance in ordinary and periodical inspections. The present state of maintenance at the nuclear power plant is mainly preventive maintenance, which is mainly conducted in a shape of time planning maintenance but partially in a shape of state monitoring maintenance for partial rotating appliances. Concretely speaking, the periodical inspection was planned on a base of daily inspection and a long term program on maintenance, and executed on a base of feedback function to think of the long term program again by evaluating the periodical inspection results. Here were introduced on the monitoring diagnosis and periodical inspection regionalization equipment, fatigue monitoring system, automatic supersonic wave damage inspection equipment for reactor, steam evaporator heat conductive tube inspection equipment, automatic testing equipment for measuring controller, air working valve property testing equipment, as maintaining support system in the PW generation plant. (G.K.)

Ground acceleration in a nuclear power plant; Aceleracion del suelo en una central nuclear

Energy Technology Data Exchange (ETDEWEB)

Pena G, P.; Balcazar, M.; Vega R, E., E-mail: pablo.pena@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

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)

A comparison of availability and outage time of nuclear power plants

International Nuclear Information System (INIS)

Nagatomi, Yu; Matsuo, Yuhji; Murakami, Tomoko

2011-01-01

Japan has recently been urged to implement measures to increase availability for nuclear power plants in order to address energy security and greenhouse gas emission cuts. The average availability for Japan's nuclear power plants in 2009 rose from 58.0% in 2008 to 64.7%, still below levels in other major nuclear power generation countries including South Korea and the United States. Some major foreign nuclear power generation countries have kept their availability for nuclear plants at high levels at or above 90% since 1990, while others including the United States and South Korea have raised their respective factors since 2000 following the 1990s when their factors were close to the Japanese level. The latter group made ambitious efforts to raise these factors. In considering specific measures to effectively utilize existing nuclear reactors, Japan should take full account of these overseas efforts and promote discussions on overall Japanese nuclear energy and safety approaches. (author)

Current problems associated with nuclear plant construction contracts

International Nuclear Information System (INIS)

Albano, Raffaele.

1977-01-01

The expansion of nuclear electricity generating programmes has brought to the fore the problems associated with construction of this type of power plant. The paper analyses the contracts for such construction and describes the most common, the turnkey contract. The present tendency is to limit the scope of turnkey contracts to the nuclear system or simply to the reactor and this is especially common in advanced nuclear countries such as the US, Canada, Japan, UK and France, and this is also the case in Italy where the question of contracting nuclear plants is debated. In Germany the power utilities hold a large number of shares in the manufacturing industry and the turnkey contract is therefore more economically attractive. A detailed description of the contracting procedure is provided, including the suppliers' and purchasers' responsibilities, plant commissioning tests and handing over of the plant to the operator. (NEA) [fr

Application of Advanced Technology to Improve Plant Performance in Nuclear Power Plants

International Nuclear Information System (INIS)

Hashemian, H.M.

2011-01-01

Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

PWR reactors for BBR nuclear power plants

International Nuclear Information System (INIS)

Structure and functioning of the nuclear steam generator system developed by BBR and its components are described. Auxiliary systems, control and load following behaviour and fuel management are discussed and the main data of PWR given. The brochure closes with a perspective of the future of the Muelheim-Kaerlich nuclear power plant. (GL) [de

Safety provision for nuclear power plants during remaining running time

International Nuclear Information System (INIS)

Rossnagel, Alexander; Hentschel, Anja

2012-01-01

With the phasing-out of the industrial use of nuclear energy for the power generation, the risk of the nuclear power plants has not been eliminated in principle, but only for a limited period of time. Therefore, the remaining nine nuclear power plants must also be used for the remaining ten years according to the state of science and technology. Regulatory authorities must substantiate the safety requirements for each nuclear power plant and enforce these requirements by means of various regulatory measures. The consequences of Fukushima must be included in the assessment of the safety level of nuclear power plants in Germany. In this respect, the regulatory authorities have the important tasks to investigate and assess the security risks as well as to develop instructions and orders.

Nuclear plants gain integrated information systems

International Nuclear Information System (INIS)

Villavicencio-Ramirez, A.; Rodriquez-Alvarez, J.M.

1994-01-01

With the objective of simplifying the complex mesh of computing devices employed within nuclear power plants, modern technology and integration techniques are being used to form centralized (but backed up) databases and distributed processing and display networks. Benefits are immediate as a result of the integration and the use of standards. The use of a unique data acquisition and database subsystem optimizes the high costs of engineering, as this task is done only once for the life span of the system. This also contributes towards a uniform user interface and allows for graceful expansion and maintenance. This article features an integrated information system, Sistema Integral de Informacion de Proceso (SIIP). The development of this system enabled the Laguna Verde Nuclear Power plant to fully use the already existing universe of signals and its related engineering during all plant conditions, namely, start up, normal operation, transient analysis, and emergency operation. Integrated systems offer many advantages over segregated systems, and this experience should benefit similar development efforts in other electric power utilities, not only for nuclear but also for other types of generating plants

Loss of benefits resulting from mandated nuclear plant shutdowns

International Nuclear Information System (INIS)

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

1982-01-01

This paper identifies and discusses some of the important consequences of nuclear power plant unavailability, and quantifies a number of technical measures of loss of benefits that result from regulatory actions such as licensing delays and mandated nuclear plant outages. The loss of benefits that accompany such regulatory actions include increased costs of systems generation, increased demand for nonnuclear and often scarce fuels, and reduced system reliability. This paper is based on a series of case studies, supplemented by sensitivity studies, on hypothetical nuclear plant shutdowns. These studies were developed by Argonne in cooperation with four electric utilities

Study on risk management for operation of nuclear generation plant

International Nuclear Information System (INIS)

Yamashita, Hiroko

2012-01-01

Reputation loss is regarded as a management issue because it impacts to business and industries significantly. Reputation management is one of the approach both business and public organizations. Application of reputation management for nuclear plant management is discussed. (author)

technical guidelines for the design and construction of the next generation of nuclear power plants with pressurized water reactors

International Nuclear Information System (INIS)

2009-01-01

These technical guidelines present the opinion of the French 'Groupe Permanent charge des Reacteurs nucleaires' (GPR) concerning the safety philosophy and approach as well as the general safety requirements to be applied for the design and construction of the next generation of nuclear power plants of the PWR (pressurized water reactor) type, assuming the construction of the first units of this generation would start at the beginning of the 21. century. These technical guidelines are based on common work of the French Institut de Protection et de Surete Nucleaire (IPSN) and of the German Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). Moreover, these technical guidelines were extensively discussed with members of the German Reaktor Sicherheitskommission (RSK) until the end of 1998 and further with German experts. The context of these technical guidelines must be clearly understood. Faced with the current situation of nuclear energy in the world, the various nuclear steam supply system designers are developing new products, all of them claiming their intention of obtaining a higher safety level, by various ways. GPR believes that, for the operation of a new series of nuclear power plants at the beginning of the next century, the adequate way is to derive the design of these plants in an 'evolutionary' way from the design of existing plants, taking into account the operating experience and the in-depth studies conducted for such plants. Nevertheless, introduction of innovative features must also be considered in the frame of the design of the new generation of plants, especially in preventing and mitigating severe accidents. GPR underlines here that a significant improvement of the safety of the next generation of nuclear power plants at the design stage is necessary, compared to existing plants. If the search for improvement is a permanent concern in the field of safety, the necessity of a significant step at the design stage clearly derives from better

The nuclear industry's plan to achieve new nuclear power plant orders in the 1990's

International Nuclear Information System (INIS)

Bayne, P.

1993-01-01

Since the Arab Oil Embargo of 1973, there has been a direct relationship between the growth in the Gross Domestic Product and the growth in the use of electricity in the United States. That close relationship between economic growth and electricity will continue. If that is true, the United States Department of Energy says this country will need between 190,000 to 275,000 megawatts of new generating capacity in the next 20 years. Electricity is one of the cleanest and most efficient uses of energy. Of all the ways to generate electricity, nuclear power plants are the cleanest, producing no air pollution and no greenhouse gases. To help supply the needed increase in electricity generating capacity, the US nuclear power industry has developed a Strategic Plan for Building New Nuclear Power Plants. The plan identified fourteen issues which must be dealt with to create the conditions under which utilities could place orders for new nuclear plants by the mid-1990's. The plan was published in November of 1990 and significant progress has been made on most of the fourteen issues. The plan and progress made are reviewed in depth

Economic impacts of electricity liberalization on the status of nuclear power generation in the United States

International Nuclear Information System (INIS)

Hattori, Toru

2015-01-01

This paper discusses the economic impact of electricity liberalization on the status of nuclear power generation in the United States. Nuclear power plants have been treated equally with other types of power plants in the liberalized electricity market. The existing nuclear power plants were thought to be competitive in liberalized wholesale electricity market. Competitive pressure from the market also facilitated efficiency improvement among the existing nuclear power plants. Although it was difficult to build new reactor, the U.S. nuclear power generators expanded capacity through up rates. In recent years, however, nuclear power plants suffer from the decline in wholesale power prices and some of them are forced to retire early. Although there are some market design issues that could be improved to maintain the efficient nuclear power plants in competitive environment, it is now argued that some additional arrangements to mitigate the investment risks of the nuclear power plants are necessary. (author)

Analysis of future nuclear power plants competitiveness with stochastic methods

International Nuclear Information System (INIS)

Feretic, D.; Tomsic, Z.

2004-01-01

To satisfy the increased demand it is necessary to build new electrical power plants, which could in an optimal way meet, the imposed acceptability criteria. The main criteria are potential to supply the required energy, to supply this energy with minimal (or at least acceptable) costs, to satisfy licensing requirements and be acceptable to public. The main competitors for unlimited electricity production in next few decades are fossil power plants (coal and gas) and nuclear power plants. New renewable power plants (solar, wind, biomass) are also important but due to limited energy supply potential and high costs can be only supplement to the main generating units. Large hydropower plans would be competitive under condition of existence of suitable sites for construction of such plants. The paper describes the application of a stochastic method for comparing economic parameters of future electrical power generating systems including conventional and nuclear power plants. The method is applied to establish competitive specific investment costs of future nuclear power plants when compared with combined cycle gas fired units combined with wind electricity generators using best estimated and optimistic input data. The bases for economic comparison of potential options are plant life time levelized electricity generating costs. The purpose is to assess the uncertainty of several key performance and cost of electricity produced in coal fired power plant, gas fired power plant and nuclear power plant developing probability distribution of levelized price of electricity from different Power Plants, cumulative probability of levelized price of electricity for each technology and probability distribution of cost difference between the technologies. The key parameters evaluated include: levelized electrical energy cost USD/kWh,, discount rate, interest rate for credit repayment, rate of expected increase of fuel cost, plant investment cost , fuel cost , constant annual

Nuclear power plant V-1

International Nuclear Information System (INIS)

1999-01-01

In this leaflet the short history of commissioning of Bohunice V-1 NPP is reviewed (beginning of construction 24 April 1972; First controlled reactor power, Reactor Unit 1 (RU1): 27 November 1978, Reactor Unit 2 (RU2): 15 March 1980; Connection to the grid: RU1 17 December 1978, RU2 26 March 1980; Commercial operation: RU1 1 April 1980, RU2 7 January 1981. The scheme of the nuclear reactor WWER 440/V230 is depicted. The major technological equipment (primary circuit, nuclear reactor, steam generators, reactor coolant pumps, primary circuit auxiliary systems, secondary circuit, turbine generators, NPP electrical equipment, and power plant control) are described. Technical data of the Bohunice V-1 NPP are presented

Radioactive waste management for German nuclear power plants

International Nuclear Information System (INIS)

Weh, R.; Methling, D.; Sappok, M.

1996-01-01

In Germany, back-end fuel cycle provisions must be made for the twenty nuclear power plants currently run by utilities with an aggregate installed power of 23.4 GWe, and the four nuclear power plants already shut down. In addition, there are the shut down nuclear power plants of the former German Democratic Republic, and a variety of decommissioned prototype nuclear power plants built with the participation of the federal government and by firms other than utilities. The nuclear power plants operated by utilities contribute roughly one third of the total electricity generation in public power plants, thus greatly ensuring a stable energy supply in Germany. The public debate in Germany, however, focuses less on the good economic performance of these plants, and the positive acceptance at their respective sites, but rather on their spent fuel and waste management which, allegedly, is not safe enough. The spent fuel and waste management of German nuclear power plants is planned on a long-term basis, and executed in a responsible way by proven technical means, in the light of the provisions of the Atomic Act. Each of the necessary steps of the back end of the fuel cycle is planned and licensed in accordance with German nuclear law provisions. The respective facilities are built, commissioned, and monitored in operation with the dedicated assistance of expert consultants and licensing authorities. Stable boundary conditions are a prerequisite in ensuring the necessary stability in planning and running waste management schemes. As producers of waste, nuclear power plants are responsible for safe waste management and remain the owners of that waste until it has been accepted by a federal repository. (orig./DG) [de

Economical aspects of a nuclear power plant project

International Nuclear Information System (INIS)

Meldonian, N.L.; Santos, E.M. dos

1992-01-01

This work describes different aspects and parameters that should be regarded as guidelines for economic evaluation of small and medium power plant projects. The main objective of an economic evaluation is to establish the plant's unitary cost and its economic figure of merit. To achieve that, a number of studies must be undertaken to compare the global competitiveness of a nuclear power plant with other energetic alternatives. These studies involve macro economy, energy generation, electricity transmission and global feasibility of the enterprise. It is concluded that the economic evaluation of a nuclear power plant should be considered as the culmination of a long process of planning at a national level. The main reasons are the investments involved, the technological developments required and political implications of the utilization of nuclear power energy. (author)

DSNP: a new approach to simulate nuclear power plants

International Nuclear Information System (INIS)

Saphier, D.

1977-01-01

The DSNP (Dynamic Simulator for Nuclear Power-plants) is a special purpose block oriented simulation language. It provides for simulations of a large variety of nuclear power plants or various parts of the power plant in a simple straightforward manner. The system is composed of five basic elements, namely, the DSNP language, the precompiler-or the DSNP language translator, the components library, the document generator, and the system data files. The DSNP library of modules includes the selfcontained models of components or physical processes found in a nuclear power plant, and various auxiliary modules such as material properties, control modules, integration schemes, various basic transfer functions etc. In its final form DSNP will have four libraries

The financing of nuclear power plants

International Nuclear Information System (INIS)

Taylor, M.

2009-01-01

Existing nuclear generating capacity plays an important role in providing secure, economic and low-carbon electricity supplies in many OECD countries. At the same time, there is increasing recognition that an expansion of nuclear power could play a valuable role in reducing future carbon dioxide emissions. However, in recent years only a handful of new nuclear power plants (NPPs) have been built in just a few OECD countries. An important reason for this is the challenges associated with financing the construction of new NPPs

Is it possible long-tern operation of Spanish nuclear power plants?