WorldWideScience

Sample records for power plants radiological

  1. Radiological respiratory protection in Angra-1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Amaral, Marcos A. do

    1996-01-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  2. Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

  3. Radiological protection and nuclear power plants

    International Nuclear Information System (INIS)

    Delpla, M.

    Dosimetric results obtained inside and outside nuclear power plants are examined with a review to proposing revision of the radiological protection standards. Dose limits are considered with regard to leukemia and genetic effects. Other topics discussed are: observed collective damage and mean risk; lethal exposure; healing and sign change of additional risk; and genetic effects of radiation on mice

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  5. Review of radiological problems of floating nuclear power plants

    International Nuclear Information System (INIS)

    Rodd, T.

    1982-01-01

    Radiological problems associated with floating nuclear power plants under both normal operation and accident conditions are discussed. In the latter case, aspects of both the airborne and liquid pathways are reviewed

  6. Radiological impact from airborne routine discharges of Coal-Fired power plant

    International Nuclear Information System (INIS)

    Norasalwa Zakaria; Rohyiza Baan; Kathiravale, Sivapalan

    2010-01-01

    Radioactivity exists everywhere in nature. We are exposed to intense and continuous natural radiation coming from the sun, cosmic radiation, telluric radiation and even to the internal radiation of our own body. The fly ash emitted from burning coal for electricity by a power plant carries into the surrounding environment 100 times more radiation than a nuclear power plant producing the same amount of energy. This paper presents the information of studies on the radiological impact from airborne routine discharge of coal-fired power plants. (author)

  7. Optimization of radiological protection in Spanish nuclear power plants

    International Nuclear Information System (INIS)

    O'Donnell, P.; Amor, I.; Butragueno, J.L.

    1997-01-01

    Optimizing the radiological protection of occupationally exposed nuclear power plant workers has become one further item in what is called the safety culture. Spanish facilities are implementing programme with this in mind, grounded on a personal motivation policy with the backing of a suitable organizational structure. (Author)

  8. Radiological protection in nuclear power plants

    International Nuclear Information System (INIS)

    Zorrilla R, S.

    2008-12-01

    This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h -1 , the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

  9. Design and realization of a dosimetry and radiology system for nuclear power plants

    International Nuclear Information System (INIS)

    Capelle, M.

    Computer-assisted acquisition of radiation exposure data and related tasks was established at an early stage at Biblis nuclear power plant of RWE. Due to the positive experience with this system a similar, more sophisticated system has been developed for the nuclear power plants at Grundremmingen, Muelheim-Kaerlich and Kalkar. This system, DORA (Dosimetry and radiological monitoring) is described in the article. (RW) [de

  10. Proposed Nuclear Power Plants in the UK-Potential Radiological Implications for Ireland

    International Nuclear Information System (INIS)

    McMahon, C.; Kelleher, K.; McGinnity, P.; Organo, C.; Smith, K.; Currivan, L.; Ryan, T.

    2013-05-01

    The UK Government has identified up to eight locations for the construction of new nuclear power plants by 2025. Five of these locations are on the Irish Sea coast. The Radiological Protection Institute of Ireland, RPII was requested by the Minister for the Environment, Community and Local Government to undertake an assessment of the potential radiological impacts on Ireland from this New Build Programme. This report presents the findings of the potential impacts on Ireland of both the anticipated routine radioactive discharges and of a range of postulated nuclear accident scenarios. The following points are the principal findings of the report. Given the prevailing wind direction in Ireland, radioactive contamination in the air, either from routine operation of the proposed nuclear power plants or accidental releases, will most often be transported away from Ireland. The routine operation of the proposed nuclear power plants will have no measurable radiological impact on Ireland or the Irish marine environment. The severe accident scenarios assessed ranged in their estimated frequency of occurrance from 1 in 50,000 to 1 in 33 million per year. The assessment used a weather pattern that maximised the transfer of radioactivity to Ireland. For the severe accident scenarios assessed, food controls or agriculture protective measures would generally be required in Ireland to reduce exposure of the population so as to mitigate potential long-term health effects. In the accident scenario with an estimated 1 in 33 million chance of occurring, short-term measures such as staying indoors would also be advised as a precautionary measure. In general, the accidents with higher potential impact on Ireland are the ones least likely to occur. Regardless of the radiological impact, any accident at the proposed nuclear power plants leading to an increase of radioactivity levels in Ireland would have a socio-economic impact on Ireland. A major accidental release of radioactivity to

  11. Proposed Nuclear Power Plants in the UK-Potential Radiological Implications for Ireland

    Energy Technology Data Exchange (ETDEWEB)

    McMahon, C.; Kelleher, K.; McGinnity, P.; Organo, C.; Smith, K.; Currivan, L.; Ryan, T.

    2013-05-15

    The UK Government has identified up to eight locations for the construction of new nuclear power plants by 2025. Five of these locations are on the Irish Sea coast. The Radiological Protection Institute of Ireland, RPII was requested by the Minister for the Environment, Community and Local Government to undertake an assessment of the potential radiological impacts on Ireland from this New Build Programme. This report presents the findings of the potential impacts on Ireland of both the anticipated routine radioactive discharges and of a range of postulated nuclear accident scenarios. The following points are the principal findings of the report. Given the prevailing wind direction in Ireland, radioactive contamination in the air, either from routine operation of the proposed nuclear power plants or accidental releases, will most often be transported away from Ireland. The routine operation of the proposed nuclear power plants will have no measurable radiological impact on Ireland or the Irish marine environment. The severe accident scenarios assessed ranged in their estimated frequency of occurrance from 1 in 50,000 to 1 in 33 million per year. The assessment used a weather pattern that maximised the transfer of radioactivity to Ireland. For the severe accident scenarios assessed, food controls or agriculture protective measures would generally be required in Ireland to reduce exposure of the population so as to mitigate potential long-term health effects. In the accident scenario with an estimated 1 in 33 million chance of occurring, short-term measures such as staying indoors would also be advised as a precautionary measure. In general, the accidents with higher potential impact on Ireland are the ones least likely to occur. Regardless of the radiological impact, any accident at the proposed nuclear power plants leading to an increase of radioactivity levels in Ireland would have a socio-economic impact on Ireland. A major accidental release of radioactivity to

  12. National radiological emergency response to the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Dela Rosa, Alumanda M.

    2011-01-01

    The Fukushima nuclear power plant accident occurred on March 11, 2011, when two natural disasters of unprecedented strengths, an earthquake with magnitude 9 followed one hour later by a powerful tsunami struck northeastern Japan and felled the external power supply and the emergency diesel generators of the Fukushima Daiichi nuclear power station, resulting in a loss of coolant accident. There were core meltdowns in three nuclear reactors with the release of radioactivity estimated to be 1/10 of what was released to the environment during the Chernobyl nuclear power plant accident in April 1986. The Fukushima nuclear accident tested the capability of the Philippine Nuclear Research Institute (PNRI) and the National Disaster Risk Reduction and Management Council (NDRRMC) in responding to such radiological emergency as a nuclear power plant accident. The PNRI and NDRRMC activated the RADPLAN for possible radiological emergency. The emergency response was calibrated to the status of the nuclear reactors on site and the environmental monitoring undertaken around the site and off-site, including the marine environment. This orchestrated effort enabled the PNRI and the national agencies concerned to reassure the public that the nuclear accident does not have a significant impact on the Philippines, both on the health and safety of the people and on the safety of the environment. National actions taken during the accident will be presented. The role played by the International Atomic Energy Agency as the central UN agency for nuclear matters will be discussed. (author)

  13. A computerized assessment and response system for radiological emergency at Diablo Canyon Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shih, C.C.; Thuillier, R.H.

    1984-01-01

    The U.S. Nuclear Regulatory Commission requires that nuclear power plants provide for rapid assessment and response in the event of a radiological emergency. At the Diablo Canyon Nuclear Power Plant, Pacific Gas and Electric Company uses a system of linked central minicomputer, satellite desktop computers and microprocessors to provide decision makers with timely and pertinent information in emergency situations. The system provides for data acquisition and microprocessing at meteorological and radiological monitoring sites. Current estimates or projections of offsite dose commitment are made in real-time by a dispersion/dose calculation model. Computerized dissemination of data and calculational results to decision makers at the government and utility levels is also available. The basic system in use is a commercially available Emergency Assessment and Response System (EARS). This generic system has been modified in-house to meet requirements specific to emergency situations at the plant. Distinctive features of the modification program includes: a highly professional man-machine interaction; consideration of site-specific factors; simulation of environmental radiology for development of drill scenarios; and concise, pertinent reports as input to decision making

  14. Radiological respiratory protection in Angra-1 Nuclear Power Plant; Protecao respiratoria radiologica na Usina Nuclear de Angra

    Energy Technology Data Exchange (ETDEWEB)

    Amaral, Marcos A. do [Furnas Centrais Eletricas S.A., Angra dos Reis, RJ (Brazil). Central Nuclear de Angra I. Div. de Protecao Radiologica e Ambiental

    1996-07-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  15. Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant

    International Nuclear Information System (INIS)

    Martinez S, R.; Cervini L, A.

    1991-01-01

    The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

  16. Radiological safety of nuclear power plants in India

    International Nuclear Information System (INIS)

    Sathish, A.V.

    2015-01-01

    Safety in nuclear power plants (NPPs) is often less understood and more talked about, thus the author wanted to share the facts to clear the myths. Safety is accorded overriding priority in all the activities. All nuclear facilities are sited, designed, constructed, commissioned and operated in accordance with strict quality and safety standards. Principles of defence in depth, redundancy and diversity are followed in the design of all nuclear facilities and their systems/components. PPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, approved standard operating and maintenance procedures, a well-defined waste management methodology, periodically rehearsed emergency preparedness and disaster management plans. The regulatory framework in the country is robust, with the independent Atomic Energy Regulatory Board (AERB) having powers to frame the policies, laying down safety standards, monitoring and enforcing all the safety provisions. As a result, India's safety record has been excellent in over 400 reactor years of operation of power reactors

  17. Atmospheric dispersion and the radiological consequences of normal airborne effluents from a nuclear power plant

    International Nuclear Information System (INIS)

    Fang, D.; Yang, L.; Sun, C.Z.

    1995-01-01

    The relationship between the consequences of the normal exhaust of radioactive materials in air from nuclear power plants and atmospheric dispersion is studied. Because the source terms of the exhaust from a nuclear power plant are relatively low and their radiological consequences are far less than the corresponding authoritative limits, the atmospheric dispersion models, their various modifications, and selections of relevant parameters have few effects on those consequences. In the environmental assessment and siting, the emphasis should not be placed on the consequence evaluation of routine exhaust of nuclear power plants, and the calculation of consequences of the exhaust and atmospheric field measurements should be appropriately, simplified. 12 refs., 5 figs., 7 tabs

  18. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  19. Preliminary study of the environmental radiological assessment for the Garigliano nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Esposito, A.M.; Sabbarese, C.; Sirignano, C.; Visciano, L.; D'Onofrio, A.D.; Lubritto, C.; Terrasi, F.

    2002-01-01

    In the last few years many nuclear installations in the world have been stopped either because they reached the end of production lifetime, or for operation problems or, like in Italy, for political decisions. This stop started the decommissioning procedure. It consists in the dismantling of the nuclear installation with appropriate controls and limitations of environmental and radiological impact which arises from these operations. The evaluation of risk and the actions needed for the population safeguard are generally inspired to the recommendations of the International Commission on Radiological Protection (ICRP), but each country faces the problem with different evaluation methodologies and calculations. That is due to different laws and environmental, social and economical context where nuclear installations are located. For this, the decommissioning operations must be separately evaluated for each nuclear installation. In this paper, we present the work carried out so far about the decommissioning of the Nuclear Power Plant of Garigliano (Caserta, Italy), which is managed by SoGIN (Societa di Gestione degli Impianti Nucleari). This Nuclear Power Plant began its activity in 1964 by using a boiling water reactor with a production of 160 MW electric power. In 1979 this nuclear installation was stopped for maintenance and operation has not been resumed until the referendum in 1986, after which all Italian nuclear plants were stopped. Now, the Nuclear Power Plant of Garigliano has the reactor isolated respect to the remaining part and all components and pipes have been drained and sealed. The underground tanks of radioactive wastes have been evacuated and decontaminated. The radioactive wastes have been completely conditioned with cementification in drums suitable to prevent outside release

  20. Radiological effects of Yatagan coal-fired power plant

    International Nuclear Information System (INIS)

    Barlas, F.; Buke, T.

    2004-01-01

    Radiation dose calculations and also limit radiation dose calculations have been carried out by the code CAP88-PC around the Yatagan coal-fired power plant environment by using the result of previous studies about maximum measured gross alpha activity in the flying ash samples as radioactive sources. A modified Gaussian plume equation is used to estimate the average dispersion of radionuclides released from up to six emitting sources. The sources maybe either elevated stacks or uniform area sources. Assessments are done for a circular grid of distances and directions for a radius up to 80 kilometers, 16 wind sectors and 20 mesh distances around the facility in calculations. The limit doses obtained from the calculations and their radiological effects have been interpreted. Finally the effects of various radionuclides have been carried out and their results have been compared with each other. (author)

  1. Implementation of a radiological emergency monitoring system for Bruce Power nuclear power plant (Canada); Implementierung eines radiologischen Umgebungsueberwachungsmesssystems fuer das Kernkraftwerk Bruce Power (Kanada)

    Energy Technology Data Exchange (ETDEWEB)

    Madaric, M. [Saphymo GmbH, Frankfurt (Germany)

    2016-07-01

    The Bruce Power nuclear power plant (BP NPP) in Ontario, Canada, is the largest nuclear generating station in the world, operating 8 nuclear reactors producing 6300 MW. In correlation with Bruce Power's safety culture, ''Safety first'' and continuous improvements are essential and substantial parts of the Bruce Power philosophy and management system. After the Fukushima nuclear accident the existing radiological emergency monitoring was analyzed and improved.

  2. Planning and preparedness for radiological emergencies at nuclear power stations

    International Nuclear Information System (INIS)

    Thomson, R.; Muzzarelli, J.

    1996-01-01

    The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

  3. Occupational Radiological Protection Principles and Criteria for Designing New Nuclear Power Plants

    International Nuclear Information System (INIS)

    2010-01-01

    Global demand for electricity continues to grow and numerous new nuclear power plants (NPPs) are being planned or constructed in NEA member countries. Most of these new NPPs will be of the third generation, and will be designed for as long as 80 years of operation. The successful design, construction and operation of these plants will depend broadly on appropriately implementing the lessons from experience accumulated to date. This case study introduces a policy and technical framework that may be used when formulating technical assistance and guidance for senior managers of NPPs, designers, manufacturers, contractors and authorities responsible for regulating occupational radiation exposure. It is aimed in particular at assisting design and license assessments of new NPPs. Although not targeting the needs of countries introducing nuclear power for the first time, this case study can also provide valuable input on occupational radiological protection issues for the implementation of new nuclear energy programmes

  4. Radiological Impact Study of the Coal-Fired Power Plant of Narcea

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Baeza, A.; Mora, J. a.; Corbacho, J. a.; Trueba, C.; Guillen, J.; Rodriguez, Miralles, Y.

    2014-04-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of {sup 2}38U, {sup 2}35U, {sup 2}32Th and also the 40K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the noncombustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the Narcea coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  5. Assessment of radiological releases to the environment from a fusion reactor power plant

    International Nuclear Information System (INIS)

    Shank, K.E.; Oakes, T.W.; Easterly, C.E.

    1978-05-01

    This report summarizes the expected tritium and activation-product inventories and presents an assessment of the potential radiological releases from a fusion reactor power plant, hypothetically located at the Oak Ridge National Laboratory. Routine tritium releases and the resulting dose assessment are discussed. Uncertainties associated with the conversion of tritium gas to tritium oxide and the global tritium cycling are evaluated. The difficulties of estimating releases of activated materials and the subsequent dose commitment are reviewed

  6. Good practices in radiological protection at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Singh, V.P.; Kumar, Sanjeev; Agrawal, Mitesh; Tiwari, S.K.; Kulhari, Praveen; Gupta, Ashok

    2016-01-01

    Radiological protection performance of nuclear power plant is assessed by collective exposure, individual average exposure, external/external exposure, personnel/surface contamination and reduction of radioactive wastes. Collective exposure is reduced by integrated comprehensive ALARA program in all aspects of nuclear plant operation and maintenance has reduced collective dose many folds. In the present paper, implementation of new good practices in Radiological Protection is presented

  7. Radiological design criteria for fusion power test facilities

    International Nuclear Information System (INIS)

    Singh, M.S.; Campbell, G.W.

    1982-01-01

    The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

  8. Development of radiological performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, B.S.; Jung, K.H.; Lee, S.H.; Jang, S.Y.

    2000-01-01

    The purpose of this work was to improve the regulatory approach to check the licensee's compliance with regulation regarding radiation protection in operating nuclear power plants (NPPs). The current domestic inspection program for NPPs requires inspectors to conduct compliance-inspection for the systems/equipment and the procedures of NPPs. In this work, we have developed a set of draft radiological performance indicators (PIs) to assess radiation safety in NPPs. The development of PIs was based on the concept that the licensees' implementation of the radiation protection program in NPPs should be able to achieve the goal of radiation protection which the International Commission on Radiological Protection (ICRP) has recommended as ICRP 60 (1991). We selected and/or developed the radiological performance indicators considering the radiation exposure network (source-environment-receptor) for NPPs. The PIs intend to be applied only to normal exposure due to normal operations including transient operational conditions, but not to potential exposure due to accidents. Also, we have chosen the receptor as workers who are occupationally exposed to radiation as well as the members of public who are exposed to radiation from radioactive effluents. The PIs intend to track the past performance rather than to expect the future performance. Finally, the individual PIs do not verify the root cause of the trend of performance; however, they provide the basis for deciding whether the procedures and work management have been properly implemented. Currently a set of 21 draft PIs has been developed for the exposure network in NPPs. For the receptor, the PIs are divided into worker individual dose, worker collective dose and public individual dose. For the environment, the PIs are related to the dose rates of controlled areas, radioactive material concentrations in controlled areas, radioactive contamination in controlled areas and at exit points, and radioactive effluent

  9. Radiological protection in nuclear power plants; La proteccion radiologica en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zorrilla R, S. [CFE. Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

    2008-12-15

    This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h{sup -1}, the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  11. A model for radiological consequences of nuclear power plant operational atmospheric releases

    International Nuclear Information System (INIS)

    Kocar, Cemil; Soekmen, Cemal Niyazi

    2009-01-01

    A dynamic dose and risk assessment model is developed to estimate radiological consequences of atmospheric emissions from nuclear power plants. Internal exposure via inhalation and ingestion, external exposure from clouds and radioactivity deposited on the ground are included in the model. The model allows to simulate interregional moves of people and multi-location food supply in the computational domain. Any long-range atmospheric dispersion model which yields radionuclide concentrations in air and on the ground at predetermined time intervals can easily be integrated into the model. The software developed is validated against radionuclide concentrations measured in different environmental media and dose values estimated after the Chernobyl accident. Results obtained using the model compare well with dose estimates and activities measured in foodstuffs and feedstuffs

  12. Radiological effects of a nuclear power plant on a river system, as demonstrated by the Gundremmingen BWR on the Danube

    International Nuclear Information System (INIS)

    Herrmann, H.; Ruf, M.; Huebel, K.; Luensmann, W.

    1975-01-01

    The Gundremmingen Nuclear Power Plant (boiling water reactor, 237 MW(e)), on the Upper Danube, has been in operation since 1967. Radiological data have been collected throughout its period of operation. The behaviour of the radioactive waste products in the ecological system of the Upper Danube (water, sediments, suspended solids, water-plants, fish) has been analysed in connection with environmental contamination, the uptake capacity of the Danube, and the possible pathways to man. As a result of the investigations, it seems possible to build further nuclear power plants on the Danube, if their rates of release of radioactivity are similar to those at Gundremmingen. (author)

  13. Mobile radiological monitoring around Nuclear Power Plant site at Tarapur

    International Nuclear Information System (INIS)

    Patil, S.S.; Saindane, S.S.; Sharma, R.; Suri, M.M.K.; Pradeepkumar, K.S.; Sharma, D.N.; Rao, D.D.

    2008-01-01

    Real time mobile radiological monitoring around nuclear facilities is required for establishing background radiation dose rate data and to detect any increase in the radiation level which is attributable to the atmospheric releases from Nuclear facilities. Mobile radiation survey using mobile monitoring systems was carried out in the Emergency Planning Zone around Tarapur Atomic Power station during plant operation, taking the wind direction also into consideration. For identifying the potential difficulties during an emergency scenario and to understand the variation of the measured values several systems/instruments were used simultaneously for mapping the dose rates. As demonstrated during this monitoring programme, 40mm x 40mm NaI(Tl) detector based Portable Mobile Gamma Spectrometry System (PMGSS) which is attached with a GPS can acquire and store large amount of gamma spectra tagged with positional coordinates and can enhance the capacity of decision makers during any accidental situation. The average of dose rates measured from various locations around Tarapur Atomic Power Station is 70 - 80 nGy.h -1 . The higher dose rate in the range of 110-125 nGy.h -1 measured at one of the location is due to higher concentration of natural radioactivity mainly by 40 K which was confirmed by the gamma spectrometric measurement. (author)

  14. Evaluation of Radiological Impacts on the Operating Kartini Reactor and Natural Radioactivity of the Site Plan of Nuclear Power Plant Area

    International Nuclear Information System (INIS)

    Yazid, M; Sutresna, G; Sulistyono, A; Ngasifudin

    1996-01-01

    This radiological impacts evaluation covered of radioactivity in water, soil, grass, air samples and ambient gamma radiation that have been carried out in the Kartini reactor area and in the site plan of nuclear power plan are at Ujung Lemah Abang, Jepara, Central Java. The aim of this research was to determine that radiological impacts in the environment around the Kartini reactor compared to natural radioactivity for site plan of nuclear power plan area. The radioactivity in the water, soil and grass samples ware measured by low background beta counting system and were identified by low background gamma spectrometer. The radioactivity in the air samples was measured by beta portable counting system and the ambient gamma radiation was measured by portable high pressurized ionization chamber model RSS-112 Reuther-Stokes. The reactor data measurement was compared to the site plan of nuclear power plant area data for evaluation of radiological impacts on the operating reactor. From the evaluation and comparison can be concluded there are no indication of the radionuclide release from the reactor operation. The average radiactivity in the water, soil grass and air sample from the reactor area were between 0.17 - 0.61 Bq/1; 0,47 - 0,74 Bq/g; 4.43 - 4.60 Bq/g.ash and 49.53 - 70.90 x 10 Bq/cc. The average radioactivity of those sample from the nuclear power plant area were between 0.06-0.90 Bq/I; 0.02-0.86 Bq/g; 1.68-8.07 Bq/g.ash and 65.0-152.3 x 10 Bq/cc. The ambient gamma radiation were between 6.9-36.7 urad/h for the reactor area and 6.8-19.2 urad/h for the nuclear power plant area

  15. An aerial radiological survey of the Fort Calhoun Nuclear Power Plant and surrounding area, Fort Calhoun, Nebraska

    International Nuclear Information System (INIS)

    1994-05-01

    An aerial radiological survey was conducted over the Fort Calhoun Nuclear Power Plant in Fort Calhoun, Nebraska, during the period June 19 through June 28, 1993. The survey was conducted at an altitude of 150 feet (46 meters) over a 25-square-mile (65-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Fort Calhoun Nuclear Power Plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 12 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and potassium. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey was conducted on August 9 and 10, 1972, before the plant began operation. Exposure rates measured in both surveys were consistent with normal terrestrial background

  16. A study on the food consumption rates for off-site radiological dose assessment around Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun

    2008-01-01

    The internal dose by food consumption mostly accounts for radiological dose of public around Nuclear Power Plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commission) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in 2001∼2002. Also, the food consumption rates for maximum individual are re-estimated

  17. Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

    International Nuclear Information System (INIS)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

    1996-01-01

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

  18. Risk analysis for nuclear power plants

    International Nuclear Information System (INIS)

    Koelzer, W.

    1983-01-01

    The German risk analysis program for nuclear power plants aiming at the man and the environment is presented. An accident consequence model to calculate the radiological impact and the potential health effects is described. (E.G.) [pt

  19. Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

  20. Aerial radiological survey of the area surrounding the St. Lucie Power Plant, Fort Pierce, Florida

    International Nuclear Information System (INIS)

    Feimster, E.L.

    1979-06-01

    An airborne radiological survey of an 1100 km 2 area surrounding the St. Lucie Power Plant was conducted 1 to 8 March 1977. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from the normal background emitters. Count rates observed at 150 m altitude are converted to equivalent exposure rates at 1 m above the ground and are presented in the form of an isopleth map. Ground exposure rates measured with small portable instruments and soil sample analysis agreed with the airborne data. Geological data are presented in an isopleth map of rock and soil types. Also included is a brief description of the vegetation and terrain surrounding the site

  1. The National Institute of Nuclear Research (ININ) and its participation in the External Radiological Emergency Plans at Laguna Verde Power plant

    International Nuclear Information System (INIS)

    Suarez, G.

    1998-01-01

    In this article it is described the form in which the ININ participates in the External Radiological Emergency Plan at Laguna Verde Power plant. It is set the objective, mission and organization of this plan. The responsibilities and activities that plan has assigned are mentioned also the organization to fulfil them and the obtained results during 9 years of participation. (Author)

  2. Architect engineer balance-of-plant radiological design considerations

    International Nuclear Information System (INIS)

    Piccot, A.R.

    1975-01-01

    Methods which are or may be used by Architect Engineers in dealing with the problems of radiological safety in the design of a nuclear power plant are discussed. The bases and basic requirements for a radiation protection program are briefly noted. Requirements in the areas of planning, organization, responsibilities and implementation of radiation protection are discussed. Lists of safety tasks which should be performed during the various design phases are presented

  3. Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants. Interim report

    International Nuclear Information System (INIS)

    1980-01-01

    The purpose of this document is to provide a common reference and interim guidance source for: state and local governments and nuclear facility operators in the development of radiological emergency response plans and preparedness in support of nuclear power plants; and Nuclear Regulatory Commission (NRC), Federal Emergency Management Agency (FEMA) and other Federal agency personnel engaged in the review of state, local government, and licensee plans and preparedness

  4. Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  5. Radiological characterization of nuclear plants under decommissioning

    International Nuclear Information System (INIS)

    Mincarini, M.

    1989-01-01

    In the present work a description of major problems encountered in qualitative and quantitative radiological characterization of nuclear plants for decommissioning and decontamination purpose is presented. Referring to several nuclear plant classes activation and contamination processes, direct and indirect radiological analysis and some italian significant experience are descripted

  6. Inquiry into the radiological consequences of power uprates at light-water reactors worldwide

    International Nuclear Information System (INIS)

    Bilic Zabric, Tea; Tomic, Bojan; Lundgren, Klas; Sjoeberg, Mats

    2007-05-01

    In Sweden, most of the nuclear power plants are planning power uprates within the next few years. The Dept. of Occupational and Medical Exposures at the Swedish Radiation Protection Agency, SSI, has initiated a research project to investigate the radiological implications of power uprates on light-water reactors throughout the world. The project was divided into three tasks: 1. A compilation of power uprates of light-water reactors worldwide. The compilation contains a technical description in brief of how the power uprates were carried out. 2. An analysis of the radiological consequences at four selected Nuclear Power Plants, which was the main objective of the inquiry. Affects on the radiological and chemical situation due to the changed situation were discussed. 3. Review of technical and organisational factors to be considered in uprate projects to keep exposures ALARA. The project was carried out, starting with the collecting of information on the implemented and planned uprates on reactors internationally. The information was catalogued in accordance with criteria focusing on radiological impact. A detailed analysis followed of four plants selected for uprates chosen according to established criteria, in line with the project requirements. The selected plants were Olkiluoto 1 and 2, Cofrentes, Asco and Tihange. The plants were selected with design and operation conditions close to the Swedish plants. All information was compiled to identify good and bad practices that are impacting on the occupational exposure. Important factors were discussed concerning BWRs and PWRs which affect radiation levels and occupational exposures in general, and especially at power uprates. Conclusions related to each task are in detail presented in a particular chapter of the report. Taking into account the whole project and its main objective the following conclusions are considered to be emphasized: Optimisation of the work processes to limit the duration of the time spent in

  7. Inquiry into the radiological consequences of power uprates at light-water reactors worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Bilic Zabric, Tea; Tomic, Bojan; Lundgren, Klas; Sjoeberg, Mats

    2007-05-15

    In Sweden, most of the nuclear power plants are planning power uprates within the next few years. The Dept. of Occupational and Medical Exposures at the Swedish Radiation Protection Agency, SSI, has initiated a research project to investigate the radiological implications of power uprates on light-water reactors throughout the world. The project was divided into three tasks: 1. A compilation of power uprates of light-water reactors worldwide. The compilation contains a technical description in brief of how the power uprates were carried out. 2. An analysis of the radiological consequences at four selected Nuclear Power Plants, which was the main objective of the inquiry. Affects on the radiological and chemical situation due to the changed situation were discussed. 3. Review of technical and organisational factors to be considered in uprate projects to keep exposures ALARA. The project was carried out, starting with the collecting of information on the implemented and planned uprates on reactors internationally. The information was catalogued in accordance with criteria focusing on radiological impact. A detailed analysis followed of four plants selected for uprates chosen according to established criteria, in line with the project requirements. The selected plants were Olkiluoto 1 and 2, Cofrentes, Asco and Tihange. The plants were selected with design and operation conditions close to the Swedish plants. All information was compiled to identify good and bad practices that are impacting on the occupational exposure. Important factors were discussed concerning BWRs and PWRs which affect radiation levels and occupational exposures in general, and especially at power uprates. Conclusions related to each task are in detail presented in a particular chapter of the report. Taking into account the whole project and its main objective the following conclusions are considered to be emphasized: Optimisation of the work processes to limit the duration of the time spent in

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

    International Nuclear Information System (INIS)

    1993-03-01

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

  9. Description of the operation and radiological impact of a spanish coastal coal-fired power station

    International Nuclear Information System (INIS)

    Corbacho, Jose A.; Baeza, Antonio; Robles, Beatriz; Mora, Juan C.; Cancio, David

    2008-01-01

    The 'Litoral' Coal-Fired Power Plant (LCFPP) is situated in the town of Carboneras (Almeria) in southern Spain. Its nominal output power is 1589 M We. The fuel used is imported sub-bituminous coal supplied by collier vessels, and unloaded in a port annexed to the plant. The climate of the area is semi-arid mediterranean, with particularly low rainfall. The plant's radiological impact was studied considering various exposure pathways for the workers and the general public. In particular, inhalation and external exposure contributions to the effective dose due to the different materials involved in the operation (coals, fly ash, and bottom ash) were evaluated. Alpha spectrometry was used to characterize radiologically the airborne particulates collected in aerosol filters at points within the installation, and to determine 210 Po levels in aerosols collected in filters placed around the power station. High resolution gamma spectrometry was used to characterize coal and ash samples from the plant, and soil samples collected outside the installation within a radius of 5 km. A dose rate monitor was used to measure the ambient dose equivalent at different points inside and outside the plant. Samples of the seawater used in the plant and of products for human consumption produced nearby were also collected and characterized radiologically. The effective dose was evaluated following a realistic approach based principally on experimental measurements and in situ observations, complemented with mathematical models when necessary. The resulting estimated effective doses for selected representative groups of workers and general public were all below the reference levels used in this work. (author)

  10. The coal fired power plant of Vado Ligure

    International Nuclear Information System (INIS)

    Ferrara, V.

    1987-01-01

    The problem of radiological impact from radioactive effluents released by the forecast new coal-fired power plant of Vado Ligure, is examinated. Using health physic metodologies of evaluation, the highest levels of dose equivalents to the population are computed. Taken into account the possible errors due to conservative models adopted, it is concluded that the induced radiological risks are to be considered negligible, both referring to the actual natural radiological levels in the environment, and considering the maximum permissible levels stated in international raccomandations

  11. Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants: Criteria for utility offsite planning and preparedness: Final report

    International Nuclear Information System (INIS)

    Podolak, E.M. Jr.; Sanders, M.E.; Wingert, V.L.; Donovan, R.W.

    1988-09-01

    The Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) have added a supplement to NUREG-0654/FEMA-REP-1, Rev. 1 that provides guidance for the development, review, and evaluation of utility offsite radiological emergency response planning and preparedness for those situations in which state and/or local governments decline to participate in emergency planning. While this guidance primarily applies to plants that do not have full-power operating licenses, it does have relevance to operating nuclear power plants

  12. Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant; Participacion del ININ en el plan de emergencia radiologica externo de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Martinez S, R; Cervini L, A [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-07-01

    The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

  13. Millstone nuclear power plant emergency system assessment

    International Nuclear Information System (INIS)

    Akhmad Khusyairi

    2011-01-01

    U.S.NRC determined an obligation to build a nuclear power plant emergency response organization for both on-site and off-site. Millstone Nuclear Power Plants have 3 nuclear reactors and 2 of 3 still in commercial operation. Reactor unit 1, BWR type has been permanently shut down in 1998, while the two others, units 2 and 3 obtain the extended operating license respectively until 2035 and 2045. As a nuclear installation has the high potential radiological impact, Millstone nuclear power plant emergency response organization must establish both on-site or off-site. Emergency response organization that is formed must involve several state agencies, both state agencies and municipality. They have specific duties and functions in a state of emergency, so that protective measures can be undertaken in accordance with the community that has been planned. Meanwhile, NRC conduct their own independent assessment of nuclear power plant emergencies. (author)

  14. Radiological Impact Associated to Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) from Coal-Fired Power Plants Emissions - 13436

    International Nuclear Information System (INIS)

    Dinis, Maria de Lurdes; Fiuza, Antonio; Soeiro de Carvalho, Jose; Gois, Joaquim; Meira Castro, Ana Cristina

    2013-01-01

    Certain materials used and produced in a wide range of non-nuclear industries contain enhanced activity concentrations of natural radionuclides. In particular, electricity production from coal is one of the major sources of increased human exposure to naturally occurring radioactive materials. A methodology was developed to assess the radiological impact due to natural radiation background. The developed research was applied to a specific case study, the Sines coal-fired power plant, located in the southwest coastline of Portugal. Gamma radiation measurements were carried out with two different instruments: a sodium iodide scintillation detector counter (SPP2 NF, Saphymo) and a gamma ray spectrometer with energy discrimination (Falcon 5000, Canberra). Two circular survey areas were defined within 20 km of the power plant. Forty relevant measurements points were established within the sampling area: 15 urban and 25 suburban locations. Additionally, ten more measurements points were defined, mostly at the 20-km area. The registered gamma radiation varies from 20 to 98.33 counts per seconds (c.p.s.) corresponding to an external gamma exposure rate variable between 87.70 and 431.19 nGy/h. The highest values were measured at locations near the power plant and those located in an area within the 6 and 20 km from the stacks. In situ gamma radiation measurements with energy discrimination identified natural emitting nuclides as well as their decay products (Pb-212, Pb-2142, Ra-226, Th-232, Ac-228, Th-234, Pa-234, U- 235, etc.). According to the results, an influence from the stacks emissions has been identified both qualitatively and quantitatively. The developed methodology accomplished the lack of data in what concerns to radiation rate in the vicinity of Sines coal-fired power plant and consequently the resulting exposure to the nearby population. (authors)

  15. Upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

    International Nuclear Information System (INIS)

    Llado Castillo, R.; Aguilar Pacheco, R.

    1998-01-01

    The work shows the results obtained in the upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

  16. Radiological investigation in the boiler's maintenance operations in a Coal-Fired power plant

    International Nuclear Information System (INIS)

    Robles, Beatriz; Mora, Juan C.; Cancio, David; Baeza, Antonio; Corbacho, Jose A.

    2008-01-01

    As part of a study being performed in the four biggest coal-fired power plants in Spain, the formation of scales of radioisotopes in parts of the heat recovery system was investigated. This effect should be more important in the case of 210 Po and 210 Pb. Thereby, it is likely in given specific chemical conditions that scales could be formed with a high concentration of 210 Pb, probably in secular equilibrium with 210 Po and 210 Bi. Those scales could reach activity concentrations of some hundreds of Bq g -1 . In order to study within the boiler this scale formation, an investigation during the maintenance operations programmed in the 'Compostilla' coal-fired power plant (Ponferrada-Spain) was carried out. Those operations are performed each 2-3 years and last for around 30 or 40 days. Measurements of ambient dose equivalent (H * (10)) in the boiler before and after the entrance of the operators, together with beta surface contamination on the bottom ashes attached in the walls and on the tubes, were performed. The last measurements were carried out for screening purposes in order to select those areas on the tubes which could present Po scales. Even if chemical conditions are in general oxidising within the boiler, since conditions are not homogeneous, some zones were localized in which surface contamination was measured. In these spots, samples were collected and then measured in the laboratory. Moreover, an analysis of maintenance tasks, used personal protection equipment, working times and other important parameters was also carried out. This analysis is important in order to perform radiological evaluations, as realistic as possible, of the effective doses that could be received by maintenance operators. In the present study, the values of the measurements performed and the results of the assessment of the effective doses for the workers are presented. (author)

  17. Coal-fired power plant: airborne routine discharges

    International Nuclear Information System (INIS)

    Zeevaert, T.

    2005-01-01

    The radiological impact from non-nuclear industries is a growing matter of concern to stake holders and regulators. It has been demonstrated that atmospheric discharges from coal-fired power plants can lead to higher dose-impacts to critical groups of the population than nuclear power plants. In Belgium, in the frame of an agreement between electricity producers and national authorities, measures were taken in conventional power plants to restrict airborne discharges of SO 2 , NO x and suspended particles. In the 500 MWe coal-fired power plant of Langerlo, a flue gas purification system was installed, consisting of a denitrification unit and a desulphurization unit, next to the electrostatic dust filter units. These measures have also an important effect on the radioactive atmospheric discharges. The objective of this study was to assess the radiological impact of the airborne releases of the power plant under normal working conditions and in particular the influence of the installation of the flue gas purification system. As a first step, we measured the natural radioactivity content of the coal and the radium content of the fly ash . The quantities of the other radioelements discharged through the chimney, were estimated, assuming the same behaviour as radium, except for the more volatile lead and polonium, which will condense preferably on finer ash particles, against which the electro filters are less effective. (A concentration factor of 4 has been adopted). The radon, present in the coal, is assumed to be discharged completely through the chimney. The atmospheric transport, dispersion and deposition of the discharged radionuclides were modelled, applying the bi-Gaussian plume model IFDM. For the calculations, we used hourly averages of the meteorological observations at Mol over the year 1991. The transfers of the radionuclides from air and soil to the biospheric media, exposing man, were calculated with our biosphere model and the radiological impact to the

  18. Impact of power plant KRSKO on the environment

    International Nuclear Information System (INIS)

    Hak, Nena; Lulic, Stipe

    1993-01-01

    The Sava river is among the largest rivers in the Republic of Croatia. It drains 95.000 square kilometers before meeting the Danube River. The Sava river and its surroundings we being exploited in agriculture, forestry, power generation (one nuclear power plant and several thermal power plants), oil transportation, gravel extraction and recreation. At last, the Sava River is the major source of fresh water for industry and population. Different authorized institutions from the Republic of Slovenia and the Republic of Croatia are included in programs of nonradiological and radiological monitoring of Nuclear Power Plant Krsko (NPPK). Quarterly, the institutions from the Republic of Croatia, NPP Krsko and the Ministry of Energy of the Republic of Croatia, submit public information in the Republic of Croatia about NPP Krsko operation and its environmental impact

  19. Radiological impact of airborne effluents of coal-fired and nuclear power plants

    International Nuclear Information System (INIS)

    McBride, J.P.; Moore, R.E.; Witherspoon, J.P.; Blanco, R.E.

    1977-06-01

    Radiological impact of naturally occurring radionuclides in airborne effluents of a model coal-fired steam plant is evaluated assuming a release to the atmosphere of 1 percent of the ash in the coal burned and compared with the impact of radioactive materials in the airborne effluents of model light-water reactors. The principal exposure pathway for radioactive materials released from both types of plants is ingestion of contaminated foodstuffs. For nuclear plants immersion in the airborne effluents is also a significant factor in the dose commitment. Assuming that the coal burned contains 1 ppM uranium and 2 ppM thorium together with their decay products and using the same impact analysis methods used in evaluating nuclear facilities, the maximum individual dose commitments from the coal plant for the whole body and most organs (except the thyroid) are shown to be greater than those from a pressurized-water reactor (PWR) and, with the exception of the bone and kidney doses, less than those from a boiling-water reactor (BWR). With the exception of the bone dose, the maximum individual dose commitments from the coal plant are less than the numerical design guideline limits listed for light-water reactors (LWRs). Population dose commitments from the coal plant are higher than those from either nuclear plant

  20. The radiological accident of Goiania and the acceptance by the public of new nuclear power plants

    International Nuclear Information System (INIS)

    Meldonian, N.L.; Mattos, L.A.T.

    1998-01-01

    Misunderstandings on the peaceful uses and the safety of nuclear energy have been a leading cause of apprehension in Brazilian public opinion. A lack of knowledge of the characteristics and destination of radioactive wastes and negative media coverage of the use of nuclear energy have aggravated this situation. Believing that applications of nuclear energy are harmful to the population's welfare and the environment, Brazilian public opinion is opposed to the utilization of nuclear energy, and in particular to the construction of new nuclear power plants. For this reason, the Brazilian nuclear sector should promote a more intensive programme of public discussion, directed not solely at the technical and scientific communities, but also at the Brazilian public at large. Such a campaign would contribute towards a better understanding by Brazilian society of the different uses of nuclear energy and would present arguments in support of the benefits of this form of energy. Moreover, a campaign of this kind would show that negative associations about the use of electricity derived from nuclear power, which are based on the Goiania radiological accident, are not justified. (author)

  1. An aerial radiological survey of the Enrico Fermi Atomic Power Plant and surrounding area, Newport, Michigan

    International Nuclear Information System (INIS)

    1986-05-01

    An aerial radiological survey was performed over the area surrounding the Enrico Fermi Atomic Power Plant during the period 27 to 30 May 1986. The survey covered a 64-square-kilometer (25-square-mile) area around the plant. The deteted radiation was due to the presence of varying concentrations of naturally-occurring radioactive materials. Radionuclides of the uranium and thorium decay chains and radioactive potassium were found. For the majority of the survey area, the inferred radiation exposure rate levels varied between 10 and 12 microroentgens per hour (μR/h). The reported exposure rate values included an estimated cosmic ray contribution of 3.7 μR/h. Ground-based measurements, conducted concurrently with the aerial survey, were compared to the inferred aerial results. Pressurized ionization chamber readings and a group of soil samples were acquired at five locations within the survey area. The exposure rate values obtained from these ground-based measurements were in good agreement with the corresponding inferred aerial values. No evidence was found of any radioactive contamination which might have occurred as a result of plant operations. This conclusion was supported by the results of the soil samples analyses and the comparison of the current survey data with those obtained in September 1970. 7 refs., 5 figs., 1 tab

  2. Relative radiation hazards of coal based and nuclear power plants

    International Nuclear Information System (INIS)

    Mishra, U.C.

    1983-04-01

    Coal, like most materials found in nature, contains trace quantities of naturally occurring radionuclides. However, low concentrations may become important if large quantities of coal are burnt in thermal power plants. Therefore a study was performed to determine the radioactivity in coal, in fly-ash and slag and assess the importance of radioactive emissions from thermal power plants. The results were compared to the radiological impact of nuclear power stations. Based on these data, theoretical estimates for the population living within 80km from power stations indicate that the collective dose commitments of coal-fired plants are one order of magnitude higher than those for BWR-type nuclear plants. Measurements taken in the vicinity of coal-fired plants were comparable to those for nuclear plants, i.e. within the range of variation of natural background radiation in India

  3. Radiological effects

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Environmental monitoring in the vicinity of the Calvert Cliffs Nuclear Power Plant has been shown the radiation dose to the public from plant operation to be quite small. Calculations from the reported release rates yield 0.2 mrem whole body dose and 0.6 mrem skin dose for the calendar quarter of maximum release. Radioactivity discharges to the Chesapeake Bay have resulted in detectable concentrations of /sup 110m/Ag, 58 Co, and 60 Co in sediments and shellfish. The area yielding samples with detectable concentrations of plant effluents extends for roughly six miles up and down the western shore, with maximum values found at the plant discharge area. The radiation dose to an individual eating 29 doz oysters and 15 doz crabs (5 kg of each) taken from the plant discharge area would be about 4/1000 mrem whole body dose and 0.2 mrem gastrointestinal tract dose (about 0.007% and 0.5% of the applicable guidelines, respectively.) Comparison of these power plant-induced doses with the fluctuations in natural radiation dose already experienced by the public indicates that the power plant effects are insignificant. The natural variations are tens of times greater than the maximum doses resulting from Calvert Cliffs Power Plant. Although operations to date provide an insufficient basis to predict radiological impact of the Calvert Cliffs Plant over its operational lifetime, available data indicate that the plant should continue to operate with insignificant radiological impact, well within all applicable guidelines

  4. Carolina Power and Light Company's computerized Radiological Information Management System

    International Nuclear Information System (INIS)

    Meyer, B.A.

    1987-01-01

    Carolina Power and Lignt Company has recently implement a new version of their computerized Radiological Information management System. The new version was programmed in-house and is run on the Company's mainframe computers. In addition to providing radiation worker dose histories and current dose updates, the system provides real-time access control for all three of the Company's nuclear plants such as respirator and survey equipment control and inventory, TLD QC records, and many other functions

  5. Trends in radiation protection: possible effects on fusion power plant design

    International Nuclear Information System (INIS)

    Eurajoki, Tapani; Frias, Manuel Pascual; Orlandi, Sergio

    2003-01-01

    Since the design of fusion power plants involves long-term issues, ranging over several decades, it is useful to try to foresee under what kind of regulations the first fusion plants are to be operated. Application of present radiological regulations and practice to a fusion power plant concept is considered. The current design phase of fusion power plants motivates the top-down dose assessment, but it is crucial to aim at bottom-up assessments to ensure radiation doses as low as reasonably achievable. Since several issues, relating both to our knowledge on radiation as well as to the practice of radiation protection, may change in the future, it is necessary to continuously follow the development in the further design of fusion power plants

  6. Some aspects of nuclear power plant safety under war conditions

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  7. An aerial radiological survey of the Perry Nuclear Power Plant and surrounding area, North Perry, Ohio: Date of survey: April 1987

    International Nuclear Information System (INIS)

    Fritzsche, A.E.

    1987-01-01

    An aerial radiological survey was conducted over the Perry Nuclear Power Plant, North Perry, Ohio. The purpose of the 234-square-kilometer (91-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. An exposure rate contour map at 1 meter above ground level was constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates increased from 0 microroentgens per hour (μR/h) over Lake Erie to 9 μR/h as the distance from Lake Erie increased. Only one anomalous area appears on the map, which is due to an excess of Bi-214 in a landfill area. Ground-based exposure rate measurements and soil samples were obtained to support the aerial data. Oblique aerial photographs of the plant were also acquired during the survey. 6 refs., 6 figs., 1 tab

  8. Radiological controls integrated into design

    Energy Technology Data Exchange (ETDEWEB)

    Kindred, G.W. [Cleveland Electric Illuminating Co., Perry, OH (United States)

    1995-03-01

    Radiological controls are required by law in the design of commercial nuclear power reactor facilities. These controls can be relatively minor or significant, relative to cost. To ensure that radiological controls are designed into a project, the health physicist (radiological engineer) must be involved from the beginning. This is especially true regarding keeping costs down. For every radiological engineer at a nuclear power plant there must be fifty engineers of other disciplines. The radiological engineer cannot be an expert on every discipline of engineering. However, he must be knowledgeable to the degree of how a design will impact the facility from a radiological perspective. This paper will address how to effectively perform radiological analyses with the goal of radiological controls integrated into the design package.

  9. Socio/economic/ecological impacts of nuclear power plants

    International Nuclear Information System (INIS)

    Golden, J.; Watson, J.

    1975-01-01

    A nuclear facility has both radiological and non-radiological effects on the environment. To minimize radiological effects, limits are set on releases of radioactive materials that will cause either direct or indirect exposure (such as the food chain). Exposure pathways for man and other organisms are described with comparisons of typical calculated doses and design objective doses. Non-radiological impacts of nuclear plants are classified as ecological-physical and socio/economic considerations, which include eighteen areas affected during each phase of the nuclear facility cycle. The ecological-physical environment is impacted in the areas of hydrology, terrestrial and aquatic ecology, and air and water quality. The socio-economic environment is impacted in areas of land use, tax base, employment, economic stimulus, relocation, lifestyle, demand for service, aesthetics, and power needs. Case studies of large construction projects are described in the appendix

  10. An aerial radiological survey of the Oyster Creek Nuclear Power Plant and surrounding area, Forked River, New Jersey. Date of survey: September 18--25, 1992

    International Nuclear Information System (INIS)

    Hopkins, H.A.; McCall, K.A.

    1994-05-01

    An aerial radiological survey was conducted over the Oyster Creek Nuclear Power Plant in Forked River, New Jersey, during the period September 18 through September 24, 1992. The survey was conducted at an altitude of 150 feet (46 meters) over a 26-square-mile (67-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Oyster Creek Nuclear Power plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 4 and 10 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey of the power plant was conducted in August 1969 during its initial startup phase. Exposure rates and radioactive isotopes revealed in both surveys were consistent and within normal terrestrial background levels

  11. Soil radioactivity levels and radiation hazard assessment around a Thermal Power Plant

    International Nuclear Information System (INIS)

    Kumar, Mukesh; Kumar, Pankaj; Sharma, Somdutt; Agrawal, Anshu; Kumar, Rajesh; Prajith, Rama; Sahoo, B.K.

    2016-01-01

    Coal based thermal power plants further enhance the level of radioactivity in the environment, as burning of coal produces fly ash that can be released into the environment containing traces of 238 U, 232 Th and their decay products. Therefore, coal fired power plants are one of the major contributor towards the Technologically Enhanced Natural Radiation (TENR). Keeping this in view, a study of natural radioactivity in the soil of twenty five villages within 5 km radius around the Harduaganj Thermal Power Plant, Aligarh, UP, India is going on under a BRNS major project, to know the radiological implications on general population living around this plant

  12. Power uprates in nuclear power plants: international experiences and approaches for implementation

    International Nuclear Information System (INIS)

    Kang, Ki Sig

    2008-01-01

    The greater demand for electricity and the available capacity within safety margins in some operating NPPs are prompting nuclear utilities to request license modification to enable operation at a higher power level, beyond their original license provisions. Such plant modifications require an in-depth safety analysis to evaluate the possible safety impact. The analysis must consider the thermo hydraulic, radiological and structural aspects, and the plant behavior, while taking into account the capability of the structures, systems and components, and the reactor protection and safeguard systems set points. The purpose of this paper is to introduce international experiences and approaches for implementation of power uprates related to the reactor thermal power of nuclear power plants. The paper is intended to give the reader a general overview of the major processes, work products, issues, challenges, events, and experiences in the power uprates program. The process of increasing the licensed power level of a nuclear power plants is called a power uprate. One way of increasing the thermal output from a reactor is to increase the amount of fissile material in use. It is also possible to increase the core power by increasing the performance of the high power bundles. Safety margins can be maintained by either using fuels with a higher performance, or through the use of improved methods of analysis to demonstrate that the required margins are retained even at the higher power levels. The paper will review all types of power uprates, from small to large, and across various reactor types, including light and heavy water, pressurized, and boiling water reactors. Generally, however, the content of the report focuses on power uprates of the stretch and extended type. The International Atomic Energy Agency (IAEA) is developing a technical guideline on power uprates and side effects of power uprates in nuclear power plants

  13. Natural radionuclides in soil profiles surrounding the largest coal-fired power plant in Serbia

    Directory of Open Access Journals (Sweden)

    Tanić Milan N.

    2016-01-01

    Full Text Available This study evaluates the influence of the largest Serbian coal-fired power plant on radionuclide concentrations in soil profiles up to 50 cm in depth. Thirty soil profiles were sampled from the plant surroundings (up to 10 km distance and analyzed using standard methods for soil physicochemical properties and gamma ray spectrometry for specific activities of natural radionuclides (40K, 226Ra and 232Th. Spatial and vertical distribution of radionuclides was determined and analyzed to show the relations between the specific activities in the soil and soil properties and the most influential factors of natural radionuclide variability were identified. The radiological indices for surface soil were calculated and radiological risk assessment was performed. The measured specific activities were similar to values of background levels for Serbia. The sampling depth did not show any significant influence on specific activities of natural radionuclides. The strongest predictor of specific activities of the investigated radionuclides was soil granulometry. All parameters of radiological risk assessment were below the recommended values and adopted limits. It appears that the coal-fired power plant does not have a significant impact on the spatial and vertical distribution of natural radionuclides in the area of interest, but technologically enhanced natural radioactivity as a consequence of the plant operations was identified within the first 1.5 km from the power plant. [Projekat Ministarstva nauke Republike Srbije br. III43009 i br. III41005

  14. Radiological Impact Study of the Coal-Fired Power Plant of Velilla; Estudio del Impacto Radiologico de la Central Termica de Carbon de Velilla

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Mora, J. c.; Trueba, C.; Rodriguez, J.; Baeza, A.; Corbacho, J. a.; Guillen, J.; Miralles, Y.

    2013-10-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of 238U, 235U, 232Th and also the 40K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the non-combustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the Velilla coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  15. Radiological Impact Study of the Coal-Fired Power Plant of Lada; Estudio del Impacto Radiologico de la Central Termica de Carbon de Lada

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Baeza, A.; Mora, J. C.; Corbacho, J. A.; Trueba, C.; Guillen, J.; Rodriguez, J.; Miralles, Y.

    2014-02-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of 238{sup U}, 235{sup U}, 232{sup T}h and also the 40K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the noncombustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the Lada coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  16. War protected underground siting of nuclear power plants -a summary

    International Nuclear Information System (INIS)

    1974-06-01

    In connection with studies concerning the need of war protected nuclear power production the technical and economical conditions with war protection of nuclear power plants have been studied within CDL. Comprehensively one have shown that no technical construction obstacles for siting a nuclear power plant underground exist that the additional costs for underground siting with price level mid 1973 are some 175-250 MSwCr (In today's price level 250 MSwCr will probably correspond to some 300 MSwCr per unit) and that the construction time is some one year longer than for an above ground plant. A study ought to examine more closely the consequences of underground siting from a radiological point of view and what demands on that occasion ought to be put on the technical design. (author)

  17. Radiological mapping of emergency planning zone of Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Pujari, R.N.; Saindane, Shashank; Narsaiah, M.V.R.; Solase, S.S.; Chaudbury, Probal; Kumar, Deepak; Gautam, Y.P.; Sharma, A.K.; Kumar, Avinash

    2016-01-01

    As a part of emergency preparedness programme, environmental radiation monitoring of Emergency Planning Zone (EPZ) (16 km radius) of Nuclear Power Plants (NPPs) is being carried out periodically. An environmental radiation monitoring of EPZ of Narora Atomic Power Station (NAPS) was carried out by installing various state-of-the-art mobile radiation monitoring systems in a vehicle and soil samples were collected from 40 locations. Around 200 important villages within EPZ were monitored and the radiological mapping of the monitored area is shown. The average dose rate recorded was 125 ± 28.8 nGy h -1 . Analysis of the collected dose rate data and the soil samples indicate normal background radiation level in the area

  18. Restart of the Armenia-2 Nuclear Power Station: Radiological emergency preparedness considerations for the nearby American community

    International Nuclear Information System (INIS)

    Vargo, G.J.; Sherwood, G.L.

    1996-01-01

    The Armenia Nuclear Power Station is located at Metsamor, approximately 30 km NW of the capital, Yerevan. The station, a two-unit, first-generation Soviet-designed VVER-440/270 pressurized water reactor plant was closed following the 1988 earthquake near Spitak. Because of a severe energy shortage the Government of Armenia has undertaken a program to recommission Unit 2. The plant design and circumstances surrounding its closure caused members of the U.S. Embassy staff and the American community in Armenia to express concerns for their safety in the event of a radiological emergency. In response, two representatives from the U.S. Department of Energy's International Nuclear Safety Program traveled to Armenia to review the Status of radiological emergency preparedness, meet with the American community, and make protective action recommendations. In this presentation we examine the major issues associated with recommissioning of Armenia-2, the challenges involved with developing a radiological emergency preparedness program for the American community, and our recommendations for protective actions in the absence of a strong communications and radiological monitoring infrastructure

  19. Environmental impacts of radiological consequences during the anticipated transients without scram (ATWS) events in nuclear power reactors

    International Nuclear Information System (INIS)

    El-Kafas, A.A.

    2011-01-01

    Anticipated transients without scram (ATWS), is one of the (worst case) accidents could happen if the system that provides a highly reliable means of shutting down the reactor (scram system )fails to work during a reactor event (anticipated transient).It has two general characteristics: (1) Initiation by a transient anticipated to occur one or more times in the life of reactor and ,(2) Assumed to proceed without scram.The types of events considered are those used for designing the plant .The evaluation of the radiological consequences during the assessment of the nuclear events,especially ATWS in nuclear power reactors, is very essential for environmental studies and public safety. In this paper, the root cases for nuclear events and dose calculation are presented. Scenario of accident sequences together with radiological impacts is illustrated for loss of coolant accident (LOCA) for a typical pressurized water reactor nuclear power plant. Recommendations for mitigating or preventing the release of radiation and high radioactive materials to environment are presented.

  20. Objective indicators of organizational performance at nuclear power plants

    International Nuclear Information System (INIS)

    Olson, J.; Osborn, R.N.; Jackson, D.H.; Shikiar, R.

    1986-01-01

    This report summarizes research conducted on the development and validation of organizational performance measures at operating nuclear power plants. Publicly available data, including measures from Licensee Event Reports, operating and outage data, and violations data, are used to predict penultimate measures of plant safety. Penultimate measures of safety include potentially significant events, overexposures and near overexposures, and several radiological release measures. The 1981 and 1982 performance measures are used in correlation and regression analyses to predict performance on the penultimate safety measures in 1982 and 1983. Many of the plant performance measures are consistently predictive of the frequency of potentially significant events. No strong, consistent predictors emerge for exposures or liquid radiological releases. Several performance measures are consistent predictors of gaseous releases. The regression analyses indicate that the predictors do not tend to combine in consistent, multivariate patterns, and controls for plant age, size, type, region, and fuel cycle stage do not substantially affect the results. The analysis concludes that existing performance data do appear to be predictive of some aspects of plant safety performance. The report recommends that more reliable, summary performance measures be created by combining several of the performance measures tested in the current analysis

  1. New aspects in the radiological emergency plan outside the Nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Alva L, S.

    1991-01-01

    The Mexican government through the National Commission of Nuclear Safety and Safeguards has imposed to the Federal Commission of Electricity to fulfill the requirement of having a functional Emergency Plan and under the limits that the regulator organisms in the world have proposed. The PERE (Plan of External Radiological Emergency) it has been created for the Nuclear Power station of Laguna Verde, Mexico

  2. Radiation risk perception by radiation professionals. Survey results just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant

    International Nuclear Information System (INIS)

    Miura, Miwa; Hayashida, Rika; Takao, Hideaki; Matsuda, Naoki; Ono, Koji

    2013-01-01

    From October to December 2010, just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant, 71 radiation professionals belonging to the radiation facilities in Japan were asked what they consider as a 'safe' dose of radiation for themselves, their spouse, parents, children, brothers and friends. Although the 'safe' dose varied widely from less than 1 mSv/y to higher than 100 mSv/y, the average dose was 35.6 mSv/y that was around the middle point between the exposure dose limits for annual average (20 mSv/y) and for any single year (50 mSv/y). Similar results were obtained from another surveys for the members of Japan Radioisotope Association (36.9 mSv/y) and for the Oita Prefectural Hospital (36.8 mSv/y). Among the family members and friends, the minimum average 'safe' dose was 8.5 mSv/y for children, to whom 50% of responders claimed the 'safe' dose less than 1 mSv. Gender, age and specialty of the responder also affected the 'safe' dose. These findings suggest that the perception of radiation risk varies widely and that the legal exposure dose limit derived from the regulatory science may act as an anchor of safety even in radiation professionals. The different level of risk perception for different target groups in radiation professionals appears similar to those in non-professional whole population. The gap between these characteristics of real radiation professionals and the generally accepted picture of radiation professionals might take a part in a state of confusion after the radiological accident. (author)

  3. Estimated radiological effects of the normal discharge of radioactivity from nuclear power plants in the Netherlands with a total capacity of 3500 MWe

    International Nuclear Information System (INIS)

    Lugt, G. van der; Wijker, H.; Kema, N.V.

    1977-01-01

    In the Netherlands discussions are going on about the installation of three nuclear power plants, leading with the two existing plants to a total capacity of 3500 MWe. To have an impression of the radiological impact of this program, calculations were carried out concerning the population doses due to the discharge of radioactivity from the plants during normal operation. The discharge via the ventilation stack gives doses due to noble gases, halogens and particulate material. The population dose due to the halogens in the grass-milk-man chain is estimated using the real distribution of grass-land around the reactor sites. It could be concluded that the population dose due to the contamination of crops and fruit is negligeable. A conservative estimation is made for the dose due to the discharge of tritium. The population dose due to the discharge in the cooling water is calculated using the following pathways: drinking water; consumption of fish; consumption of meat from animals fed with fish products. The individual doses caused by the normal discharge of a 1000 MWe plant appeared to be very low, mostly below 1 mrem/year. The population dose is in the order of some tens manrems. The total dose of the 5 nuclear power plants to the dutch population is not more than 70 manrem. Using a linear dose-effect relationship the health effects to the population are estimated and compared with the normal frequency

  4. 75 FR 20867 - DTE Energy; Enrico Fermi Atomic Power Plant, Unit 1

    Science.gov (United States)

    2010-04-21

    ... Power Plant, Unit 1 Environmental Assessment and Finding of No Significant Impact for an Exemption From... County, Michigan. Environmental Assessment Identification of Proposed Action The proposed action is in... the Michigan Department of Natural Resources and the Environment, Radiological Protection and Medical...

  5. Radiological Impact Study of the Coal-Fired Power Plant of Abono; Estudio del Impacto Radiologico de la Central Termica de Carbon de Abono

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Baeza, A.; Mora, J. C.; Corbacho, J. A.; Trueba, C.; Guillen, J.; Rodriguez, J.; Miralles, Y.

    2014-04-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of {sup 2}38U, {sup 2}35U, {sup 2}32Th and also the {sup 4}0K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the noncombustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the Abono coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  6. Radiological Impact Study of the Coal-Fired Power Plant of Anllares; Estudio del Impacto Radiologico de la Central Termica de Carbon de Anllares

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Baeza, A.; Mora, J. C.; Corbacho, J. A.; Trueba, C.; Guillen, J.; Rodriguez, J.; Miralles, Y.

    2014-04-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of {sup 2}38U, {sup 2}35U, {sup 2}32Th and also the 40K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the noncombustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the Anllares coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  7. Radiological Impact Study of the Coal-Fired Power Plant of Meirama; Estudio del Impacto Radiologico de la Central Termica de Carbon de Meirama

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Baeza, A.; Mora, J. C.; Corbacho, J. A.; Trueba, C.; Guillen, J.; Rodriguez, J.; Miralles, Y.

    2014-04-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of {sup 2}38U, {sup 2}35U, {sup 2}32Th and also the 40K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the noncombustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the Meirama coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  8. Simulation of {sup 137}Cs transport and deposition after the Chernobyl Nuclear Power Plant accident and radiological doses over the Anatolian Peninsula

    Energy Technology Data Exchange (ETDEWEB)

    Simsek, V.; Pozzoli, L.; Unal, A.; Kindap, T., E-mail: kindap@itu.edu.tr; Karaca, M.

    2014-11-15

    The Chernobyl Nuclear Power Plant (CNPP) accident occurred on April 26 of 1986, it is still an episode of interest, due to the large amount of radionuclides dispersed in the atmosphere. Caesium-137 ({sup 137}Cs) is one of the main radionuclides emitted during the Chernobyl accident, with a half-life of 30 years, which can be accumulated in humans and animals, and for this reason the impacts on population are still monitored today. One of the main parameters in order to estimate the exposure of population to {sup 137}Cs is the concentration in the air, during the days after the accident, and the deposition at surface. The transport and deposition of {sup 137}Cs over Europe occurred after the CNPP accident has been simulated using the WRF-HYSPLIT modeling system. Four different vertical and temporal emission rate profiles have been simulated, as well as two different dry deposition velocities. The model simulations could reproduce fairly well the observations of {sup 137}Cs concentrations and deposition, which were used to generate the ‘Atlas of Caesium deposition on Europe after the Chernobyl accident’ and published in 1998. An additional focus was given on {sup 137}Cs deposition and air concentrations over Turkey, which was one of the main affected countries, but not included in the results of the Atlas. We estimated a total deposition of 2–3.5 PBq over Turkey, with 2 main regions affected, East Turkey and Central Black Sea coast until Central Anatolia, with values between 10 kBq m{sup −2} and 100 kBq m{sup −2}. Mean radiological effective doses from simulated air concentrations and deposition has been estimated for Turkey reaching 0.15 mSv/year in the North Eastern part of Turkey, even if the contribution from ingestion of contaminated food and water is not considered, the estimated levels are largely below the 1 mSv limit indicated by the International Commission on Radiological Protection. - Highlights: • Chernobyl Nuclear Power Plant accident

  9. Methodology for evaluating radiological consequences of the management of very low-level solide waste arising from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Smith, G.M.; Hemming, C.R.; Clark, J.M.; Chapuis, A.M.; Garbay, H.

    1985-01-01

    In this report a methodology is described, and illustrated by examples, for the evaluation of individual doses and collective dose commitments arising as a result of various management modes for very low-level solid wastes arising from the decommissioning of nuclear power plants. Estimates have been made of the masses of materials activated and contaminated to within three concentration limits, 0.37, 3.7 and 37 Bq g-1, at three times after reactor shutdown, 5 y, 25 y and 100 y. The disposal options considered are shallow land burial, at a municipal landfill site or at the reactor site, and disposal on the seabed in coastal waters or the deep ocean. It is assumed that there is no special treatment to reduce or eliminate the potential radiological hazard. Consideration has also been given to the radiological impact of recycling of contaminated steel. The radiological impacts of all the management options for the wastes considered were found to be small. It may therefore be acceptable to allow such very low-level wastes to be disposal of without special restrictions provided that the level and type of activity of the wastes can be verified. In addition the health detriment cost associated with all the management options is small, so it is likely that other factors such as transport and engineering costs will be more important in final decisions about the management of these wastes

  10. Background activity values from the nuclear power plants at the spanish coast

    International Nuclear Information System (INIS)

    Montesinos, M.

    1979-01-01

    The radiological data obtained from gross alpha and beta measurements are exposed. Also the activity of differents long lived radionuclides from a significant number of the Cantabric coast sea biota samples is given, where the Lemoniz nuclear power plant is located, as well as those from the Mediterranean coast, where the Vandellos nuclear power plant is sitting. The activity transfer through the different steps of the food-chain in each biota sample, as well as the activity values for sediments and water are presented. Eventually, a comparatif study of the background activity values between the two coasts mentioned above, is made. Also a comparison between the preoperational and operational values for the operating Vandellos nuclear power plant is described. (author)

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

    International Nuclear Information System (INIS)

    Umbara, Heru; Yatim, Sofyan

    1998-01-01

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

  12. Radiological protection report 2016

    International Nuclear Information System (INIS)

    2017-06-01

    In the radiological protection report 2016, the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an overview of the radiological protection in its area of supervision. Part A of the report deals with protecting the staff of nuclear power plants from the dangers of ionising radiation. It also includes a list of the personal doses accumulated by the staff, broken down using various parameters. Applying the optimisation imperative, it has been proved possible to significantly reduce the annual collective doses in Switzerland's nuclear power plants since they came on stream thanks to major efforts by the operators. In 2016, a total of 6,153 people measured accumulated 2,877 person-mSv. The collective doses have reached a low level corresponding to the radiological condition of the plants and the scope of the work required to be performed in controlled zones (e.g. non-destructive materials testing). ENSI will continue to follow the trend for collective doses and assess the reasons for local variances as well as for measures initiated. The individual doses for people employed in ENSI's area of supervision in 2016 showed a maximum figure of 10 mSv and a mean value of 0.5 mSv which was significantly below the dose limit of 20 mSv for occupational radiation exposure. The discharge of radioactive substances with the exhaust air and waste water from nuclear power plants are dealt with in Part B of the report. In 2016, nuclear power plant operators again met the admissible release limits set by the authorities, in some cases by a considerable margin. The emissions of Swiss nuclear power plants led to a dose of less than 0.01 mSv per year in the direct neighbourhood. A comparison with the average annual radiation dose for the Swiss population of 5.5 mSv shows that the relevant contribution from nuclear power plants lies in the area of one percent of this figure. Effluents from Swiss nuclear power plants were also below the target of 1 GBq per year set by ENSI

  13. Safety in nuclear power plants

    International Nuclear Information System (INIS)

    Koeberlein, K.

    1987-01-01

    In nuclear power plants large amounts of radioactive fission products ensue from the fission of uranium. In order to protect the environment, the radioactive material is confined in multiple 'activity barriers' (crystal matrix of the fuel, fuel cladding, coolant boundary, safety containment, reactor building). These barriers are protected by applying a defense-in-depth concept (high quality requirements, protection systems which recognize and terminate operational incidents, safety systems to cope with accidents). In spite of a favorable safety record of German nuclear power plants it is obvious - and became most evident by the Chernobyl accident - that absolute safety is not achievable. At Chernobyl, however, design disadvantages of that reactor type (like positive reactivity feedback of coolant voiding, missing safety containment) played an important role in accident initiation and progression. Such features of the Russian 'graphite-moderated pressure tube boiling water reactor' are different from those of light water reactors operating in western countries. The essential steps of the waste management of the nuclear fuel cycle ('Entsorgung') are the interim storage, the shipment, and the reprocessing of the spent fuel and the final repository of radioactive waste. Reprocessing means the separation of fossil material (uranium, plutonium) from radioactive waste. Legal requirements for radiological protection of the environment, which are identical for nuclear power plants and reprocessing plant, are complied with by means of comprehensive filter systems. Safety problems of a reprocessing plant are eased considerably by the fact that system pressures, process temperatures and energy densities are low. In order to confine the radioactive waste from the biosphere for a very long period of time, it is to be discarded after appropriate treatment into the deep geological underground of salt domes. (orig./HP) [de

  14. Possible uses and applications of drones in a nuclear power plant

    International Nuclear Information System (INIS)

    Celis del A, L.; Palacios, J.; Rivero, T.; Valero, D.

    2016-09-01

    The versatility of drones is one of the strengths that have led to the rapid development of this technology, as they adapt relatively easily to new applications, presenting considerable advantages such as greater energy efficiency, longer life and a significant lower operation cost than manned systems. The current applications of the drones, in addition to the military, are very wide and varied. The nuclear industry represents an important area of opportunity for drones, mainly in response to radiological emergencies, since in this case there is a latent risk of the general population being exposed to high radiation doses. Drones can be used in environments with high chemical and radiological toxicity without endangering human lives. Some of the possible applications of the drones in a nuclear power plant are: perimeter surveillance in physical security, where equipped with a high definition camera can be used as support to physical security systems in general; visual inspection at sites, structures, equipment and pipelines, etc., as part of preventive maintenance in order to avoid the loss of material due to corrosion, oxidation, cracking, subsidence; the visual inspection through thermo-graphic images to be able to detect hot spots in some critical element; measurement and radiological mapping on surfaces to maintain monitoring of radiological safety at nuclear power plant facilities; the monitoring of environmental parameters and the Environmental Impact Assessment to obtain important information to determine the environmental impact of a given area; and accident support by providing information that allows staff to size the magnitude of the damage. (Author)

  15. Water management of the Dukovany nuclear power plant

    International Nuclear Information System (INIS)

    Rabusic, P.

    1990-01-01

    Industrial water for the Dukovany nuclear power plant is taken from a reservoir built on the Jihlava river. The volume of the reservoir is 17.1 million m 3 . The water taken serves mainly as the make-up water for the cooling circuit and is treated by clearing; it is also used for the preparation of demineralized water for making up the condensate circuit and for the preparation of soft water for making up the heat piping. The consumption of industrial water is 1 to 2 m 3 /s. Waste waters are released into rainwater drainage, sewage drainage and industrial water drainage. Waste waters are segregated according to the place of their origin and are purified, mainly on ion exchangers and on an evaporator. In normal conditions, they are returned to the operation. Concentrated liquid residues and solid wastes will be stored by using the multiple containment system. The most important radioisotopes that may be present in nuclear power plant waste waters, the water and radionuclide balance of the Dukovany nuclear power plant, and chemical and radiological data on the Dukovany waste waters (1989) are tabulated. (P.A.). 6 refs

  16. Regression analysis of radiological parameters in nuclear power plants

    International Nuclear Information System (INIS)

    Bhargava, Pradeep; Verma, R.K.; Joshi, M.L.

    2003-01-01

    Indian Pressurized Heavy Water Reactors (PHWRs) have now attained maturity in their operations. Indian PHWR operation started in the year 1972. At present there are 12 operating PHWRs collectively producing nearly 2400 MWe. Sufficient radiological data are available for analysis to draw inferences which may be utilised for better understanding of radiological parameters influencing the collective internal dose. Tritium is the main contributor to the occupational internal dose originating in PHWRs. An attempt has been made to establish the relationship between radiological parameters, which may be useful to draw inferences about the internal dose. Regression analysis have been done to find out the relationship, if it exist, among the following variables: A. Specific tritium activity of heavy water (Moderator and PHT) and tritium concentration in air at various work locations. B. Internal collective occupational dose and tritium release to environment through air route. C. Specific tritium activity of heavy water (Moderator and PHT) and collective internal occupational dose. For this purpose multivariate regression analysis has been carried out. D. Tritium concentration in air at various work location and tritium release to environment through air route. For this purpose multivariate regression analysis has been carried out. This analysis reveals that collective internal dose has got very good correlation with the tritium activity release to the environment through air route. Whereas no correlation has been found between specific tritium activity in the heavy water systems and collective internal occupational dose. The good correlation has been found in case D and F test reveals that it is not by chance. (author)

  17. 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

  18. Multiple external hazards compound level 3 PSA methods research of nuclear power plant

    Science.gov (United States)

    Wang, Handing; Liang, Xiaoyu; Zhang, Xiaoming; Yang, Jianfeng; Liu, Weidong; Lei, Dina

    2017-01-01

    2011 Fukushima nuclear power plant severe accident was caused by both earthquake and tsunami, which results in large amount of radioactive nuclides release. That accident has caused the radioactive contamination on the surrounding environment. Although this accident probability is extremely small, once such an accident happens that is likely to release a lot of radioactive materials into the environment, and cause radiation contamination. Therefore, studying accidents consequences is important and essential to improve nuclear power plant design and management. Level 3 PSA methods of nuclear power plant can be used to analyze radiological consequences, and quantify risk to the public health effects around nuclear power plants. Based on multiple external hazards compound level 3 PSA methods studies of nuclear power plant, and the description of the multiple external hazards compound level 3 PSA technology roadmap and important technical elements, as well as taking a coastal nuclear power plant as the reference site, we analyzed the impact of off-site consequences of nuclear power plant severe accidents caused by multiple external hazards. At last we discussed the impact of off-site consequences probabilistic risk studies and its applications under multiple external hazards compound conditions, and explained feasibility and reasonableness of emergency plans implementation.

  19. LNG plant combined with power plant

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-06-01

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

  20. LNG plant combined with power plant

    International Nuclear Information System (INIS)

    Aoki, I.; Kikkawa, Y.

    1997-01-01

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

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

    International Nuclear Information System (INIS)

    Eko Rudi Iswanto and Siti Alimah

    2010-01-01

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

  2. Management of nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    Kueffer, K.

    1980-01-01

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

  3. Radiological Impact Study of the Coal-Fired Power Plant of La Robla; Estudio del Impacto Radiologico de la Central Termica de Carbon de La Robla

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Mora, J. C.; Trueba, C.; Rodriguez, J.; Baeza, A.; Corbacho, J. A.; Guillen, J.; Miralles, Y.

    2013-07-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of 238{sup U}, 235{sup U}, 232{sup T}h and also the 40{sup K}, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the non-combustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the La Robla coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  4. Radiological Impact Study of the Coal-Fired Power Plant of La Robla; Estudio del Impacto Radiologico de la Central Termica de Carbon de La Robla

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Baeza, A.; Mora, J. C.; Corbacho, J. A.; Trueba, C.; Guillen, J.; Rodriguez, J.; Miralles, Y.

    2014-04-01

    Coal, fuel used in thermal power plants for electricity production, contains variable concentrations of naturally occurring radionuclides from natural disintegration series of {sup 2}38U, {sup 2}35U, {sup 2}32Th and also the 40K, which are enhanced in the wastes and coproducts due to the industrial process. For this reason, natural radionuclides which are part of the noncombustible fraction of coal, except those volatiles which incorporate directly to the flue gases, concentrates and are partitioned between fly ashes and bottom ashes. This enhancement could cause, to the workers of the installation and to members of the public around the plant, an increase in the exposure which should be assessed under the radiation protection point of view. Present report collect the results obtained from a screening assessment of the radiological impact derived from the normal operation of the La Robla coal-fired power plant. The project where this assessment was performed is part of a bigger project which is jointly developed by the Unit of Radiation Protection of the Public and the Environment (UPRPYMA) of CIEMAT and the Environmental Radioactivity Laboratory of the Extremadura University (LARUEX) in agreement with the Spanish Association of the Electrical Industry (ENUSA). (Author)

  5. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

    International Nuclear Information System (INIS)

    Vojtech, R.J.

    1994-03-01

    An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 μR/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation

  6. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

    Energy Technology Data Exchange (ETDEWEB)

    Vojtech, R.J.

    1994-03-01

    An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 {mu}R/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation.

  7. Operational Radiological Protection and Aspects of Optimisation

    International Nuclear Information System (INIS)

    Lazo, E.; Lindvall, C.G.

    2005-01-01

    Since 1992, the Nuclear Energy Agency (NEA), along with the International Atomic Energy Agency (IAEA), has sponsored the Information System on Occupational Exposure (ISOE). ISOE collects and analyses occupational exposure data and experience from over 400 nuclear power plants around the world and is a forum for radiological protection experts from both nuclear power plants and regulatory authorities to share lessons learned and best practices in the management of worker radiation exposures. In connection to the ongoing work of the International Commission on Radiological Protection (ICRP) to develop new recommendations, the ISOE programme has been interested in how the new recommendations would affect operational radiological protection application at nuclear power plants. Bearing in mind that the ICRP is developing, in addition to new general recommendations, a new recommendation specifically on optimisation, the ISOE programme created a working group to study the operational aspects of optimisation, and to identify the key factors in optimisation that could usefully be reflected in ICRP recommendations. In addition, the Group identified areas where further ICRP clarification and guidance would be of assistance to practitioners, both at the plant and the regulatory authority. The specific objective of this ISOE work was to provide operational radiological protection input, based on practical experience, to the development of new ICRP recommendations, particularly in the area of optimisation. This will help assure that new recommendations will best serve the needs of those implementing radiation protection standards, for the public and for workers, at both national and international levels. (author)

  8. The potential environmental impacts and the siting of proposed nuclear power plants in China

    International Nuclear Information System (INIS)

    Shi Zhongqi

    1986-01-01

    This paper reviews briefly the methodology of assessing environmental impacts from the nuclear power plants and analyses the potential radiological impacts on the environment from proposed nuclear power plants in China. Preliminary studies show that the environmental impacts of the effluents of routine release from PWRs to the proposed sites are extremely small, even if nuclear power plants are constructed either on the Bohai Sea shore with a narrow mouth or in the densely populated regions of Sunan. Thus, the suitability of sites depends mainly on the acceptability of possible exposure to the residents following postulated accidental release of radioactive materials. The paper also discusses relations between the nuclear plant siting and population distribution around the site and compares the distribution of the proposed sites in China with that of other countries sites in according to China actual situation, it is reasonable to adopt a prudent policy that the first series of nuclear power plants in China should be built in relatively low population areas

  9. Beaver Valley Power Station and Shippingport Atomic Power Station. 1984 Annual environmental report, radiological. Volume 2

    International Nuclear Information System (INIS)

    1985-01-01

    This report describes the Radiological Environmental Monitoring Program conducted during 1984 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1984. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1984. The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment. 23 figs., 18 tabs

  10. Evaluation and communication of potential risk of radionuclide contamination of foods after Fukushima nuclear power plant accident

    International Nuclear Information System (INIS)

    Sekizawa, Jun; Nakamura, Yumiko

    2011-01-01

    A large scale nuclear power plant accident happened after the great earthquake with a huge tsunami in the Eastern part of Japan in March 2011. Potential risk from radionuclide contamination in foods after the nuclear power plant accident was estimated using data of radiological food contamination from the Ministry of Health, Labour and Welfare. Data analyzed by combining nuclide, food, level of radiation detection, period, age-classified population, were compared to provisional index levels of radionuclides, and existing contamination levels in food by natural radioactive potassium. Health risk was shown to be very low or negligible considering presence of background radiological exposure from foods and the environment. Appropriate explanation of risk to various stakeholders of the society is imperative and results of trials were reported. (author)

  11. Technical specifications: Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1985-08-01

    Safety limits and limiting safety system settings are presented for the reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; and radiological environmental monitoring

  12. Sabotage at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Purvis, James W.

    1999-07-21

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  13. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Purvis, James W.

    1999-01-01

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented

  14. Course in fire protection training for nuclear power plant personnel

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  15. Understanding the nature of nuclear power plant risk

    International Nuclear Information System (INIS)

    Denning, R. S.

    2012-01-01

    This paper describes the evolution of understanding of severe accident consequences from the non-mechanistic assumptions of WASH-740 to WASH-1400, NUREG-1150, SOARCA and today in the interpretation of the consequences of the accident at Fukushima. As opposed to the general perception, the radiological human health consequences to members of the Japanese public from the Fukushima accident will be small despite meltdowns at three reactors and loss of containment integrity. In contrast, the radiation-related societal impacts present a substantial additional economic burden on top of the monumental task of economic recovery from the nonnuclear aspects of the earthquake and tsunami damage. The Fukushima accident provides additional evidence that we have mis-characterized the risk of nuclear power plant accidents to ourselves and to the public. The human health risks are extremely small even to people living next door to a nuclear power plant. The principal risk associated with a nuclear power plant accident involves societal impacts: relocation of people, loss of land use, loss of contaminated products, decontamination costs and the need for replacement power. Although two of the three probabilistic safety goals of the NRC address societal risk, the associated quantitative health objectives in reality only address individual human health risk. This paper describes the types of analysis that would address compliance with the societal goals. (authors)

  16. Safety in nuclear power plant operation, including commissioning and decommissioning. A code of practice

    International Nuclear Information System (INIS)

    1978-01-01

    Safe operation of a nuclear power plant postulates satisfactory siting, design, construction and commissioning, together with proper management and operation of the plant. This Code of Practice deals with the safety aspects of management, commissioning, operation and decommissioning of the plant. It forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. It has been prepared for the use of those responsible for the operation of stationary nuclear power plants, the main function of which is the generation of electrical and/or thermal power, and for the use of those responsible for regulating the operation of such plants. It is not intended for application to reactors used solely for experimental or research purposes. The provisions in the Code are designed to provide assurance that operational activities are carried out without undue radiological hazard to the general public and to persons on the site. It should be understood that the provisions in the Code set forth minimum requirements which shall be met in order to achieve safe operation of a nuclear power plant

  17. Are atomic power plants saver than nuclear power plants

    International Nuclear Information System (INIS)

    Roeglin, H.C.

    1977-01-01

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

  18. Regulatory practices for nuclear power plants in India

    International Nuclear Information System (INIS)

    Bajaj, S.S.

    2013-01-01

    The Atomic Energy Regulatory Board (AERB) is the national authority for ensuring that the use of ionizing radiation and nuclear energy does not cause any undue risk to the health of workers, members of the public and to the environment. AERB is responsible for the stipulation and enforcement of rules and regulations pertaining to nuclear and radiological safety. This paper describes the regulatory process followed by AERB for ensuring the safety of nuclear power plants (NPPs) during their construction as well as operation. This regulatory process has been continuously evolving to cater to the new developments in reactor technology. Some of the recent initiatives taken by AERB in this direction are briefly described. Today, AERB faces new challenges like simultaneous review of a large number of new projects of diverse designs, a fast growing nuclear power program and functioning of operating plants in a competitive environment. This paper delineates how AERB is gearing up to meet these challenges in an effective manner. (author)

  19. An aerial radiological survey of the Point Beach Nuclear Power Plant and surrounding area. Final report, October 19, 1996 - October 24, 1996

    International Nuclear Information System (INIS)

    Feimster, E.L.

    1997-12-01

    Radioactivity surrounding the Point Beach Nuclear Power Plant was measured using aerial radiological surveying techniques. The purpose of this survey was to document exposure rates and identify radiation sources within the survey area. The surveyed area included a 25-square-mile (65-square-kilometer) area, which encompasses the plant site. Data were acquired using an airborne detection system that employed sodium iodide, thallium-activated detectors. Exposure rates at 1 meter above ground level were computed from these data and plotted on a U.S. Geological Survey topographic map of the survey area. Several ground-based exposure-rate measurements were made for comparison with the aerial survey results. Exposure rates in areas surrounding the plant site varied (a) from 10-14 microroentgens per hour (μR/h) in cultivated fields, (b) from 8-10 μR/h in adjacent areas and along roadways, and (c) below 6 μR/h over waterways and wetland areas. Man-made radiation (102-202 μR/h) was found at the plant site; cobalt-60 was the primary source of activity found at the Point Beach site. No other detectable sources of man-made radioactivity were found. The exposure rates measured during this survey agreed well with those measured during the 1970 survey even though the survey methodology and parameters were significantly different

  20. Employing modern power plant simulators in nuclear power plants

    International Nuclear Information System (INIS)

    Niedorf, V.; Storm, J.

    2005-01-01

    At the present state of the art, modern power plant simulators are characterized by new qualitative features, thus enabling operators to use them far beyond the traditional field of training. In its first part, this contribution presents an overview of the requirements to be met by simulators for multivalent uses. In part two, a survey of the uses and perspectives of simulation technology in power plants is presented on the basis of experience accumulated by Rheinmetall Defence Electronics (RDE).Modern simulators are shown to have applications by far exceeding traditional training areas. Modular client - sever systems on standard computers allow inexpensive uses to be designed at several levels, thus minimizing maintenance cost. Complex development and running time environments, like the SEMS developed by RDE, have made power plant simulators the workhorses of power plant engineers in all power plant areas. (orig.)

  1. Radiological protection report 2016; Strahlenschutzbericht 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-06-15

    In the radiological protection report 2016, the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an overview of the radiological protection in its area of supervision. Part A of the report deals with protecting the staff of nuclear power plants from the dangers of ionising radiation. It also includes a list of the personal doses accumulated by the staff, broken down using various parameters. Applying the optimisation imperative, it has been proved possible to significantly reduce the annual collective doses in Switzerland's nuclear power plants since they came on stream thanks to major efforts by the operators. In 2016, a total of 6,153 people measured accumulated 2,877 person-mSv. The collective doses have reached a low level corresponding to the radiological condition of the plants and the scope of the work required to be performed in controlled zones (e.g. non-destructive materials testing). ENSI will continue to follow the trend for collective doses and assess the reasons for local variances as well as for measures initiated. The individual doses for people employed in ENSI's area of supervision in 2016 showed a maximum figure of 10 mSv and a mean value of 0.5 mSv which was significantly below the dose limit of 20 mSv for occupational radiation exposure. The discharge of radioactive substances with the exhaust air and waste water from nuclear power plants are dealt with in Part B of the report. In 2016, nuclear power plant operators again met the admissible release limits set by the authorities, in some cases by a considerable margin. The emissions of Swiss nuclear power plants led to a dose of less than 0.01 mSv per year in the direct neighbourhood. A comparison with the average annual radiation dose for the Swiss population of 5.5 mSv shows that the relevant contribution from nuclear power plants lies in the area of one percent of this figure. Effluents from Swiss nuclear power plants were also below the target of 1 GBq per year set by ENSI

  2. Estimation of radiological consequences from accidental iodine releases at nuclear power plants

    International Nuclear Information System (INIS)

    Drozdovitch, V.V.

    2001-01-01

    The radiological consequences of a beyond design-basis accident at an NPP for a VVER-1000 reactor are evaluated. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Inhalation and ingestion thyroid doses to different population sub-groups have been calculated. Using modern knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways. Thyroid doses and risk was estimated for populations living at different distances from the NPP. The comparative analysis of exposure pathways and radiological danger of the radionuclides in release during early and intermediate stage of accident has conducted. (author)

  3. Nuclear power plant safety under military threats

    International Nuclear Information System (INIS)

    Stritar, A.; Mavko, B.

    1993-01-01

    The Krsko nuclear power plant in Slovenia was probably the first in the world that found itself in the middle of a war region. A number of preventive measures performed during and immediately after the war in summer 1991 by the plant personnel as well as some of related activities of the Reactor Engineering Division of the 'Jozef Stefan' Institute are described. All efforts were aimed at the minimization of the possible public radiological consequences during a military attack. The critical safety functions in such conditions were checked. Concern was further devoted to maintenance of the core cooling in the core and to integrity of the spent fuel pit. The cold shutdown mode was found to be the most appropriate option. After selecting the cold shutdown mode as a most suitable operational state of the plant, further studies of the vulnerability were done. In addition to possible direct damage to structures, that would cause release of radioactivity, two important subjects were considered: AC and DC power supply and the ultimate heat sink. A quick analysis during the crisis has shown that the consequences of a military attack against the plant by jet fighters could be serious, but with the proper preventive measures and preparedness the environmental consequences could be minimized. (Z.S.) 1 fig., 1 ref

  4. Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

    During the 1960's and 70's the expanded use of nuclear materials to generate electricity, to provide medical benefits, and for research purposes continued to grow in the United States. While substantial effort went into constructing plants and facilities and providing for a number of redundant backup systems for safety purposes, little effort went into the development of emergency response plans for possible major radiological accidents. Unfortunately, adequate plans and procedures had not been developed to co-ordinate either state or federal emergency response assets and personnel should a major radiological accident occur. This situation became quite evident following the Three Mile Island Nuclear Reactor accident in 1979. An accident of that magnitude had not been adequately prepared for and Pennsylvania's limited emergency radiological resources and capabilities were quickly exhausted. Several federal agencies with statutory responsibilities for emergency response, including the U.S. Environmental Protection Agency (EPA), U.S. Department of Energy (DOE), Federal Emergency Management Agency (FEMA), Nuclear Regulatory Commission (NRC), and others provided extensive assistance and support during the accident. However, the assistance was not fully co-ordinated nor controlled. Following the Three Mile Island incident 13 federal agencies worked co-operatively to develop an agreement called the Federal Radiological Emergency Response Plan (FRERP). Signed in November 1985, this plan delineated the statutory responsibilities and authorities of each federal agency signatory to the FRERP. In the event of a major radiological accident, the FRERP would be activated to ensure that a co-ordinated federal emergency response would be available to respond to any major radiological accident scenario. The FRERP encompasses a wide variety of radiological accidents, not just those stemming from nuclear power plants. Activation of the FRERP could occur from major accidents involving

  5. Site selection and evaluation for nuclear power plants with respect to population distribution

    International Nuclear Information System (INIS)

    1980-01-01

    This safety guide, relating population distribution to site selection and evaluation, for nuclear power plants, forms part of the IAEA's programme, referred to as the NUSS programme (Nuclear Safety Standards). The guide presents population distribution data, requirements, examples of site screening methods, and an overview of radiological impact assessment with respect to population distribution

  6. Audit program for physical security systems at nuclear power plants

    International Nuclear Information System (INIS)

    Minichino, C.

    1982-01-01

    Licensees of nuclear power plants conduct audits of their physical security systems to meet the requirements of 10 CFR 73, Physical Protection of Plants and Materials. Section 73.55, Requirements for physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage, requires that the security programs be reviewed at least every 12 months, that the audit be conducted by individuals independent of both security management and security supervision, and that the audit program review all aspects of the physical security system: hardware, personnel, and operational and maintenance procedures. This report contains information for the Nuclear Regulatory Commission (NRC) and for the licensees of nuclear power reactors who carry out these comprehensive audits. Guidance on the overall management of the audit function includes organizational structure and issues concerning the auditors who perform the review: qualifications, independence, due professional care, and standards. Guidance in the audit program includes purpose and scope of the audit, planning, techniques, post-audit procedures, reporting, and follow-up

  7. Kansas Power Plants

    Data.gov (United States)

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

  8. Reporting nuclear power plant operation to the Finnish Centre for Radiation and Nuclear Safety

    International Nuclear Information System (INIS)

    1997-01-01

    The Finnish Centre for Radiation and Nuclear safety (STUK) is the authority in Finland responsible for controlling the safety of the use of nuclear energy. The control includes, among other things, inspection of documents, reports and other clarification submitted to the STUK, and also independent safety analyses and inspections at the plant site. The guide presents what reports and notifications of the operation of the nuclear facilities are required and how they shall be submitted to the STUK. The guide does not cover reports to be submitted on nuclear material safeguards addressed in the guide YVL 6.10. Guide YVL 6.11 presents reporting related to the physical protection of nuclear power plants. Monitoring and reporting of occupational exposure at nuclear power plants is presented in the guide YVL 7.10 and reporting on radiological control in the environment of nuclear power plants in the guide YVL 7.8

  9. Radiological consequences of atmospheric releases from coal-fired power plants

    International Nuclear Information System (INIS)

    Tveten, U.

    1985-06-01

    The report deals with the individual and collective doses resulting from radioactive materials contained in the stack releases of coal-fired power plants. A critical analysis of relevant calculations in literature is given. The different reports analyzed show a very wide range in calculated doses. To a great extent these differences may be explained by the wide range in the assumptions adopted. There is also disagreement on what exposure pathways are the most important, and what nuclides contribute most to calculated doses. A most probable value of 0.5 mrem/year for the maximum individual effective dose equivalent commitment, is indicated in the report

  10. Human factors review for nuclear power plant severe accident sequence analysis

    International Nuclear Information System (INIS)

    Krois, P.A.; Haas, P.M.

    1985-01-01

    The paper discusses work conducted to: (1) support the severe accident sequence analysis of a nuclear power plant transient based on an assessment of operator actions, and (2) develop a descriptive model of operator severe accident management. Operator actions during the transient are assessed using qualitative and quantitative methods. A function-oriented accident management model provides a structure for developing technical operator guidance on mitigating core damage preventing radiological release

  11. Hydroelectric Power Plants Dobsina

    International Nuclear Information System (INIS)

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

    1997-01-01

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

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

    International Nuclear Information System (INIS)

    Menegassi, J.

    1984-01-01

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

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

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Tanaka, Masayuki.

    1991-01-01

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

  14. The de-construction programme for EDF'S first generation power plants

    International Nuclear Information System (INIS)

    Zask, G.; Corcuff, A.

    2003-01-01

    Before 2001 EDF had adopted a 'long wait' scenario for the de-construction of nuclear power plants, consisting of waiting for a period of 5 to 10 years for IAEA level 2 (partial release of the site), then postponing the total de-construction of the facility for 25 to 50 years, in order to benefit from the natural decay of the radioactivity and thereby reduce the dosimetry of the personnel and the costs. Today, as regards the 8 power plants of the first generation and Creys-Malville, EDF has decided to undertake the total de-construction over a period of 25 years of all its reactors that have ceased commercial operation. The forecast cost of this programme amounts to Euro 3 billion. It thus intends to demonstrate its capacity to control, within the scale of the human lifespan, the entire life cycle of its nuclear power plants, while minimising the impact on man and the environment. This choice of immediate dismantling for the power plants of the first generation does not prejudge what will be done, when the time comes, for the PWR plants currently in operation. The paper has the following contents: 1. General; 2.The facilities concerned; 3. Chronological sequence adopted for de-construction; 4. Milestones and critical paths; 4.1. Simplification of the administrative procedures; 4.2. The waste channels; 4.3. Industrial organisation; 4.3.1. Creation of Centre d'Ingenierie De-construction et Environnement (CIDEN); 4.3.2. Responsibilities, interfaces and co-ordination of the various departments concerned (Role of owner: Responsibility as nuclear operator; Overall co-ordination; Operational steering of projects); 4.3.3. Internal authorization process; 4.3.4. Obtaining and maintaining skills (Training; Environment; De-construction; Radiological protection, radiology, radioecology; Processing of waste and approval of the cycle); 4.3.5. Monitoring of works and surveillance of service providers; 4.3.6. Radiological protection, environment; 4.3.7. Control of conventional

  15. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

    1985-01-01

    This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the 137 Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total 137 Cs and 134 Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984

  16. Design and development of Solar Powered Wireless Telemetering System (SPWTS) for Environmental Radiation Monitoring (ERM) of nuclear power plants

    International Nuclear Information System (INIS)

    Mariappan, Bhuvaneswari; Ramachandran, Shanmugalakshmi

    2014-01-01

    Presently, the real time environmental radiation monitoring system installed in the nuclear power plant is based on LAN. Generally data from the surveillance instrument are collected at regular intervals using a lap-top or system/units and taken to the laboratory for downloading the archival data. So a need was felt to design and develop Solar powered Wireless Telemetering System (SPWTS) for Environmental Radiation Monitoring (ERM) of Nuclear Power Plants. SPWTS is used for real-time monitoring and wireless transmission of the on-line data to the Central Control Unit (CCU) to investigate the history of monitored data. Thus, in this paper a wireless mode using Zigbee is proposed, thereby improving scalability, flexibility and continuous radiological surveillance along with data archival facility. The proposed Solar Powered Wireless Telemetering System (SPWTS) comprising of transmitter, intermediate devices and receiver units transmits the ERM data to Central Control Unit (CCU) for storage and display to RADAS unit. In order to meet the coverage distance without data loss, suitable number of repeaters/routers are configured and joined in the network. The entire wireless telemetry system is powered up by solar cells with rechargeable battery backup facility, SPWTS suitable for ERM data transmission module will replace the wired Ethernet environment by wireless mode thereby improving scalability, flexibility and continuous radiological surveillance of the gamma dose monitoring. This module also proposes solutions for wireless transmission of safety related critical data to a remote control unit. Finally, this module promotes interoperability within hierarchical framework by reducing the amount of changes that could be introduced into the existing system. (author)

  17. The influence of Goiania radiological accident on Brazilian public opinion concerning new nuclear electric plants

    International Nuclear Information System (INIS)

    Meldonian, Nelson Leon; Mattos, Luis Antonio Terribile de

    1997-01-01

    The Brazilian society is against applications of nuclear energy, mainly respecting to construction of new nuclear power plants, believing that they are harmful to population's welfare and the environment. By this reason, Brazilian nuclear sector would promote a more intensive program of public discussion, not limited to technical and scientific community. Intending to contribute to a better judgment by society about the differences between diverse employment of nuclear energy, arguments concerned to its benefits are presented, pointing out that adverse accounts to nuclear electricity based on Goiania radiological accident, are not justified

  18. Work management to optimise occupational radiological protection

    International Nuclear Information System (INIS)

    Ahier, B.

    2009-01-01

    Occupational exposures at nuclear power plants worldwide have steadily decreased since the early 1990's. Regulatory pressures, technological advances, improved plant designs and operational procedures, as low as reasonably achievable (ALARA) culture and information exchange have contributed to this downward trend. However, with the continued ageing and possible life extensions of nuclear power plants, ongoing economic pressures, regulatory, social and political evolutions, and the potential of new nuclear build, the task of ensuring that occupational exposures are kept as low as reasonably achievable continues to present challenges to radiological protection professionals

  19. The application of PSA techniques to the vital area identification of nuclear power plants

    International Nuclear Information System (INIS)

    Ha, Jae Joo; Jung, Woo Sik; Park, Chang Kue

    2005-01-01

    This paper presents a Vital Area Identification (VAI) method based on the current Fault Tree Analysis (FTA) and Probabilistic Safety Assessment (PSA) techniques for the physical protection of nuclear power plants. A structured framework of a Top Event Prevention set Analysis (TEPA) application to the VAI of nuclear power plants is also delineated. One of the important processes for physical protection in a nuclear power plant is VIA that is a process for identifying areas containing nuclear materials, Structures, Systems or Components (SSCs) to be protected from sabotage, which could directly or indirectly lead to core damage and unacceptable radiological consequences. A software VIP (Vital area Identification Package based on the PSA method) is being developed by KAERI for the VAI of nuclear power plants. Furthermore, the KAERI fault tree solver FTREX (Fault Tree Reliability Evaluation eXpert) is specialized for the VIP to generate the candidates of the vital areas. FTREX can generate numerous MCSs for a huge fault tree with the lowest truncation limit and all possible prevention sets

  20. Application of the Safety Classification of Structures, Systems and Components in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-04-01

    This publication describes how to complete tasks associated with every step of the classification methodology set out in IAEA Safety Standards Series No. SSG-30, Safety Classification of Structures, Systems and Components in Nuclear Power Plants. In particular, how to capture all the structures, systems and components (SSCs) of a nuclear power plant to be safety classified. Emphasis is placed on the SSCs that are necessary to limit radiological releases to the public and occupational doses to workers in operational conditions This publication provides information for organizations establishing a comprehensive safety classification of SSCs compliant with IAEA recommendations, and to support regulators in reviewing safety classification submitted by licensees

  1. Assessment of direct radiological risk and indirect associated toxic risks originated by Coal-Fired Power Plants

    OpenAIRE

    Dinis, M. L.; Fiúza, António; Góis, Joaquim; Carvalho, José Soeiro de; Meira Castro, A C

    2011-01-01

    Over the past few decades there has been some discussion concerning the increase of the natural background radiation originated by coal-fired power plants, due to the uranium and thorium content present in combustion ashes. The radioactive decay products of uranium and thorium, such as radium, radon, polonium, bismuth and lead, are also released in addition to a significant amount of 40K. Since the measurement of radioactive elements released by the gaseous emissions of coal power plants i...

  2. Technical specifications: Diablo Canyon Nuclear Power Plant, Unit No. 2 (Docket No. 50-323). Appendix ''A'' to License No. DPR-81

    International Nuclear Information System (INIS)

    1985-04-01

    Information is presented concerning the limiting conditions for operation for the reactivity control systems, instrumentation, power distribution limits, reactor coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, and radiological environmental monitoring

  3. A model national emergency plan for radiological accidents

    International Nuclear Information System (INIS)

    2000-07-01

    The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a result, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request

  4. Annual radiological environmental operating report: Sequoyah Nuclear Plant, 1987

    International Nuclear Information System (INIS)

    1988-04-01

    This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant in 1987. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. 2 figs., 2 tabs

  5. Independent auto evaluation of an operative radiological protection program

    International Nuclear Information System (INIS)

    Medrano L, M.A.; Rodriguez C, C.C.; Linares R, D.; Zarate M, N.; Zempoalteca B, R.

    2006-01-01

    The program of operative radiological protection of a nuclear power plant consists of multiple procedures and associate tasks that have as purpose the radiological protection of the workers of the power station. It is for this reason that the constant evaluation of the one it programs it is an important tool in the identification of their weaknesses (and strengths), so they can be assisted appropriately. In this work the main elements of the program of independent auto evaluation of the program of operative radiological protection of the Laguna Verde Central that has been developed and implemented by the National Institute of Nuclear Research are described. (Author)

  6. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    other reactor types, including innovative developments in future systems, some of the requirements may not be applicable, or may need some judgment in their interpretation. Various Safety Guides will provide guidance in the interpretation and implementation of these requirements. This publication is intended for use by organizations designing, manufacturing, constructing and operating nuclear power plants as well as by regulatory bodies. This publication establishes design requirements for structures, systems and components important to safety that must be met for safe operation of a nuclear power plant, and for preventing or mitigating the consequences of events that could jeopardize safety. It also establishes requirements for a comprehensive safety assessment, which is carried out in order to identify the potential hazards that may arise from the operation of the plant, under the various plant states (operational states and accident conditions). The safety assessment process includes the complementary techniques of deterministic safety analysis and probabilistic safety analysis. These analyses necessitate consideration of postulated initiating events (PlEs), which include many factors that, singly or in combination, may affect safety and which may: originate in the operation of the nuclear power plant itself; be caused by human action; be directly related to the nuclear power plant and its environment. This publication also addresses events that are very unlikely to occur, such as severe accidents that may result in major radioactive releases, and for which it may be appropriate and practicable to provide preventive or mitigatory features in the design. This publication does not address: external natural or human induced events that are extremely unlikely (such as the impact of a meteorite or an artificial satellite); conventional industrial accidents that under no circumstances could affect the safety of the nuclear power plant; or non-radiological effects arising

  7. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    other reactor types, including innovative developments in future systems, some of the requirements may not be applicable, or may need some judgment in their interpretation. Various Safety Guides will provide guidance in the interpretation and implementation of these requirements. This publication is intended for use by organizations designing, manufacturing, constructing and operating nuclear power plants as well as by regulatory bodies. This publication establishes design requirements for structures, systems and components important to safety that must be met for safe operation of a nuclear power plant, and for preventing or mitigating the consequences of events that could jeopardize safety. It also establishes requirements for a comprehensive safety assessment, which is carried out in order to identify the potential hazards that may arise from the operation of the plant, under the various plant states (operational states and accident conditions). The safety assessment process includes the complementary techniques of deterministic safety analysis and probabilistic safety analysis. These analyses necessitate consideration of postulated initiating events (PlEs), which include many factors that, singly or in combination, may affect safety and which may: originate in the operation of the nuclear power plant itself. Be caused by human action. Be directly related to the nuclear power plant and its environment. This publication also addresses events that are very unlikely to occur, such as severe accidents that may result in major radioactive releases, and for which it may be appropriate and practicable to provide preventive or mitigatory features in the design. This publication does not address: external natural or human induced events that are extremely unlikely (such as the impact of a meteorite or an artificial satellite). Conventional industrial accidents that under no circumstances could affect the safety of the nuclear power plant. Or non-radiological effects arising

  8. Radiological protection report 2015; Strahlenschutzbericht 2015

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-15

    In the 2015 annual report on radiological protection, the Swiss Federal Nuclear Safety Inspectorate (ENSI) reports on occupational radiation doses, releases of radioactive material and the monitoring of environmental radiation in the areas subject to its surveillance. It concludes that Swiss nuclear facilities continue to maintain a consistent approach to radiological protection. ENSI has identified an increasing public interest in data concerning radiation and has therefore introduced a number of new concepts, such as the online availability of monthly nuclear power plant releases. There is also a new development concerning the data from the network for automatic measurement of dose rates in the vicinity of nuclear power plants (MADUK) which has been in operation since 1994. It is now possible to view dose rates since 1994 averaged over periods of ten minutes, one hour and one day. A special chapter of this report deals with {sup 14}C releases, which are the subject of enquiries from interested parties. The mean annual individual occupational radiation dose remains at 0.6 mSv, being significantly less than the mean annual radiation dose of the population in Switzerland of 5.5 mSv. The highest annual individual dose was almost 11 mSv so that once again in 2015 the annual limit of 20 mSv was not exceeded. The collective doses lie within the range of past years. However, the trend towards a higher collective dose noted at the Leibstadt Nuclear Power Plant has continued. Planning by the operators of nuclear facilities in the field of radiological protection is of a high standard so that the resulting collective doses generally closely match the projected values. In 2015, nuclear power plant operators have again complied with the release limits specified by the authorities, to some extent by a considerable margin. Emissions from Swiss nuclear power plants resulted in a dose of less than 0.01 mSv per year in their immediate surroundings. Liquid releases from Swiss

  9. 1980 annual radiological environmental report. Volume 2

    International Nuclear Information System (INIS)

    1980-01-01

    This report describes the Radiological Environmental Monitoring Program conducted during 1980 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1980. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1980. There were no radioactive liquid effluents released from the Shippingport Atomic Power Station since radioactive liquids are processed and re-cycled within the plant systems. The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment

  10. Less power plants

    International Nuclear Information System (INIS)

    TASR

    2003-01-01

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

  11. Aerial radiological survey of the Diablo Canyon Nuclear Power Plant and surrounding area, Diablo Canyon, California. Date of survey: September-October 1984

    International Nuclear Information System (INIS)

    1985-03-01

    An aerial radiological survey was conducted over the area surrounding the Diablo Canyon Nuclear Power Plant in Diablo Canyon, California. The survey was conducted between 20 September and 3 October 1984. A series of flight lines parallel to the coastline were flown at an altitude of 91 meters (300 feet) and were spaced 152 meters (500 feet) apart. The survey covered an area of 250 square kilometers (100 square miles). The resulting background exposure rates over the survey area ranged from 5 to 21 microroentgens per hour (μR/h). The reported exposure rate values include an estimated cosmics ray contribution of 3.6 μR/h. Soil samples were also collected at several locations within the survey areas and analyzed in the laboratory for isotopic composition. The results of the survey showed only the presence of naturally occurring background radiation. No man-made radioactivity was detected. 4 refs., 4 figs., 4 tabs

  12. Radiological impact assessment of coal and nuclear base power plants in India

    International Nuclear Information System (INIS)

    Ramachandran, T.V.

    2007-01-01

    Environmental problems concerned with the use of coal as a fuel in thermal power plants (TPS) is due to the production of fly ash. Coal contains tracers of primordial radionuclide and its burning is one of the sources of technologically enhanced exposure from natural radionuclides. When it is burnt in TPSs, the fly ash, emitted through the stack is enriched in radionuclide and so combustion of coal on a large scale for thermal power generation assumes importance. Many of these TPSs are located in thickly populated areas. Radioactivity content of the coal from the coalfields of eastern parts of the country is found to be higher than that of other coalfields. In India coal combustion accounts nearly 73% of the total installed capacity for power generation. A sample study was carried out by this center on coal and fly ash samples collected from more than 35 TPS spread all over the country with a total installed capacity of 10000 MW(e), for their-radioactivity content. Radiation doses to the population residing within 90 km radius of each TPS have been computed. Besides another set of 15 TPSs were studied for thermal pollution emission and trace element concentration. Operation of these TPSs has resulted in effective dose commitments from doses to bones, lungs and thyroid of 200 man-Sv.y -1 and from doses to the whole body, of 70 man-Sv.y -1 . Dose commitments to the population living within 90 km radius of the TPSs and NPPs in India have been computed and have been compared. Attempt is made to assess the inhalation dose from the radioactivity released from a typical 500 MW(e) TPS and its impact related to chemical pollutants. Impact in terms of Environmental Quality Index (EQI) due to conventional pollutions have been computed and compared with those due to the nuclear power plants (NPPs). Paper gives the summary of the study. (author)

  13. The National Institute of Nuclear Research (ININ) and its participation in the External Radiological Emergency Plans at Laguna Verde Power plant; El ININ y su participacion en el Plan de Emergencia Radiologica Externo de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Suarez, G. [Instituto Nacional de Investigaciones Nucleares, Departamento de Proteccion Radiologica, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    In this article it is described the form in which the ININ participates in the External Radiological Emergency Plan at Laguna Verde Power plant. It is set the objective, mission and organization of this plan. The responsibilities and activities that plan has assigned are mentioned also the organization to fulfil them and the obtained results during 9 years of participation. (Author)

  14. Preliminary results on food consumption rates for off-site dose calculation of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun; Bang, Sun Young; Kang, Duk Won

    2005-01-01

    The Internal dose by food consumption mostly account for radiological dose of public around nuclear power plants(NPP). But, food consumption rate applied to off-site dose calculation in Korea which is the result of field investigation around Kori NPP by the KAERI in 1988. is not reflected of the latest dietary characteristics. The Ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. To update the food consumption rates of the maximum individual, the analysis of the national food investigation results and field surveys around nuclear power plant sites have been carried out

  15. Natural radionuclides from the coal in atmospheric environment of the coal fired power plants

    International Nuclear Information System (INIS)

    Antic, D.; Kostic-Soskic, M.; Milovanovic, S.; Telenta, B.

    1995-01-01

    The inhalation radiation exposure of the public in the vicinity of the selected coal fired power plants near from Belgrade (30-50 km) has been studied, using a set of data for natural radionuclides from the analysed power plants. A generalised model for analysis of radiological impact of an energy source, that includes the two-dimensional version of the cloud model, has been used for simulation of the transport of radionuclides released to the atmosphere. The inhalation dose rates for an adult are assessed and analysed during fast changeable meteorological conditions. A set of realistic meteorological conditions (wind, radiosonde sounding temperature, pressure, and humidity data) has been used for the numerical simulations. (author)

  16. Fukushima Nuclear Accident, the Third International Severe Nuclear Power Plant Accident

    International Nuclear Information System (INIS)

    Rashad, S.M.

    2013-01-01

    Japan is the world's third largest power user. Japan's last remaining nuclear reactor shutdown on Saturday 4 Th of May 2012 leaving the country entirely nuclear free. All of 50 of the nation's operable reactors (not counting for the four crippled reactors at Fukushima) are now offline. Before last year's Fukushima nuclear disaster, the country obtained 30% of its energy from nuclear plants, and had planned to produce up to 50% of its power from nuclear sources by 2030. Japan declared states of emergency for five nuclear reactors at two power plants after the units lost cooling ability in the aftermath of Friday 11 March 2011 powerful earthquake. Thousands of (14000) residents were immediately evacuated as workers struggled to get the reactors under control to prevent meltdowns. On March 11 Th, 2011, Japan experienced a sever earthquake resulting in the shutdown of multiple reactors. At Fukushima Daiichi site, the earthquake caused the loss of normal Ac power. In addition it appeals that the ensuing tsunami caused the loss of emergency Ac power at the site. Subsequent events caused damage to fuel and radiological releases offsite. The spent fuel problem is a wild card in the potentially catastrophic failure of Fukushima power plant. Since the Friday's 9.0 earthquake, the plant has been wracked by repeated explosions in three different reactors. Nuclear experts emphasized there are significant differences between the unfolding nuclear crisis at Fukushima and the events leading up to the Chernobyl disaster in 1986. The Chernobyl reactor exploded during a power surge while it was in operation and released a major cloud of radiation because the reactor had no containment structure around to. At Fukushima, each reactor has shutdown and is inside a 20 cm-thick steel pressure vessel that is designed to contain a meltdown. The pressure vessels themselves are surrounded by steel-lined, reinforced concrete shells. Chernobyl disaster was classified 7 on the International

  17. Utilization of water soluble plastics for radiological control within nuclear power plants

    International Nuclear Information System (INIS)

    Smith, R.J.; Deltete, C.P.; Homyk, W.A.; Kasprzak, L.; Robinson, P.J.

    1989-01-01

    The utilization of plastic products for radioactive contamination control within nuclear power facilities currently results in relatively large volumes of waste requiring disposal as low-level radioactive waste. The utilization of a polymer resin product that possesses comparable physical attributes to currently utilized plastic materials, but which is water soluble, has significant potential to reduce the volume of plastic waste requiring disposal as radwaste. Such a volume reduction will reduce overall plant )ampersand M costs, reduce the overall waste volume allocation utilization, and improve the regulatory perception of any plant realizing a volume reduction through plastic source minimization. This potential reduction in waste volume (and associated availability of the Low-level Waste Policy Amendments Act disposal allocation for other purposes), combined with potential economic benefits summarized above, has led to the undertaking of a detailed evaluation, presented in this paper

  18. A model national emergency response plan for radiological accidents

    International Nuclear Information System (INIS)

    1993-09-01

    The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a results, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request. 2 tabs

  19. 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

  20. Some issues on radiological consequences analysis in site selection for nuclear power stations

    International Nuclear Information System (INIS)

    Chen Xiaoqiu; Yue Huiguo

    2006-01-01

    The three considerations, Site safety and environmental protection and emergency preparedness, are the focus of attention in the evaluation of the suitability of a site for nuclear power station. This paper summarized the basic regulatory requirements for the siting of nuclear power station, described the existing problems on radiological consequences analyses during the siting stage and discussed the is- sues that need to concern in the reviewing of the radiological consequences analyses in the siting appraisal stage. (authors)

  1. Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface Water

    International Nuclear Information System (INIS)

    1997-10-01

    The Y-12 Plant conducts a surface water monitoring program in response to DOE Orders and state of Tennessee requirements under the National Pollutant Discharge Elimination System (NPDES). The anticipated codification of DOE Order 5400.5 for radiation protection of the public and the environment (10 CFR Part 834) will require an environmental radiation protection plan (ERPP). The NPDES permit issued by the state of Tennessee requires a radiological monitoring plan (RMP) for Y-12 Plant surface waters. In a May 4, 1995 memo, the state of Tennessee, Division of Water Pollution Control, stated their desired needs and goals regarding the content of RMPs, associated documentation, and data resulting from the RMPs required under the NPDES permitting system (L. Bunting, General Discussion, Radiological Monitoring Plans, Tennessee Division of Water Pollution Control, May 4,1995). Appendix A provides an overview of how the Y-12 Plant will begin to address these needs and goals. It provides a more complete, documented basis for the current Y-12 Plant surface water monitoring program and is intended to supplement documentation provided in the Annual Site Environmental Reports (ASERs), NPDES reports, Groundwater Quality Assessment Reports, and studies conducted under the Y-12 Plant Environmental Restoration (ER) Program. The purpose of this update to the Y-12 Plant RMP is to satisfy the requirements of the current NPDES permit, DOE Order 5400.5, and 10 CFR Part 834, as current proposed, by defining the radiological monitoring plan for surface water for the Y-12 Plant. This plan includes initial storm water monitoring and data analysis. Related activities such as sanitary sewer and sediment monitoring are also summarized. The plan discusses monitoring goals necessary to determine background concentrations of radionuclides, to quantify releases, determine trends, satisfy regulatory requirements, support consequence assessments, and meet requirements that releases be ''as low as

  2. Contribution of the Medical Radiology Research Center, Russian Academy of Medical Sciences, to liquidation of radionuclide contamination aftereffects in the Kaluga Region that resulted from the Chernobyl power plant accident

    International Nuclear Information System (INIS)

    Matveenko, E.G.; Berdov, B.A.; Gorobets, V.F.; Tsyplyakovskaya, L.M.; Ivanov, V.K.; Stepanenko, V.F.; Pitkevich, V.A.; Omel'chenko, V.N.; Borovikova, M.P.

    1992-01-01

    Specialists from the Medical Radiology Research Center, have been participating in liquidation of the Chernobyl power plant accident aftereffects since May-June, 1986. The basic trends of their work are mass dosimetric studies of the population of the contaminated areas, annual prophylactic check-ups of children and adolescents, pregnant and nursing women and other adults of high-risk groups (agricultural workers, patients with chronic diseases), development of recommendations for health and prophylactic measures in the districts under observation, treatment of patients from these regions, who are in need of a specialized care, at the clinic of the Center

  3. Accident prevention in power plants

    International Nuclear Information System (INIS)

    Steyrer, H.

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

  4. Radiological protection aspects of geological disposal of high-level radioactive waste

    International Nuclear Information System (INIS)

    Matsuzuru, Hideo; Kimura, Hideo

    1992-01-01

    A high-level radioactive waste, generated at a nuclear fuel reprocessing plant, will be disposed of deep, i.e., several hundred meters, within geological formations, to isolate it from the human environment. Since the waste contains significant amounts of long-lived radionuclides, such as Tc-99, I-129, Cs-135 and transuranic elements, the safety of its disposal, particularly as regards the requirement for the radiological protection of human and his environment even in the far future, is one of the essential subjects of all countries engaged in nuclear power production. The radiological protection system has long been established and applied to regulate radiation exposures to the public associated with a relatively short-term release of radioactive materials, during normal and accidental conditions, from nuclear installations such as a power plant and reprocessing plant. Radioactive waste disposal, which potentially offers a long-term radiological consequence on the public, inevitably produces a specific requirement, from the standpoint of radiological protection, that individuals and populations in the future should be accorded at least a current level of the protection. This requirement has caused a serious debate, among the community of radiological protection, on how to establish radiological protection standards and criteria, and how to establish safety assessment methodologies to demonstrate compliance with them. We have discussed in this paper on specific items such as numerical guides to indicate radiological consequences, time frames over which calculations of the consequences are to be carried out, uncertainties to be involved in the calculations, and safety assessment methodologies. (author)

  5. Management of effluents and radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    2005-01-01

    Management of effluents and radioactive waste from nuclear power plants, from the viewpoint of radiological protection, basically consists of three main themes: 1) developing and implementing actions that minimize, or where possible, eliminate generation. These actions ranging from simple awareness of people involved with the work on project modifications; 2) maintain a system of accounting and control that allows to know the characteristics of effluents and wastes, charting indicators that reveal the performance and trends of plant, and supplying data proving the compliance of national regulatory body standards; 3) Storing the solid waste generated in a safe manner, ensuring that the physical integrity of the packaged is maintained and that there is no impact to the population and the environment

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

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  7. Station blackout at nuclear power plants: Radiological implications for nuclear war

    International Nuclear Information System (INIS)

    Shapiro, C.S.

    1986-12-01

    Recent work on station blackout is reviewed its radiological implications for a nuclear war scenario is explored. The major conclusion is that the effects of radiation from many nuclear weapon detonations in a nuclear war would swamp those from possible reactor accidents that result from station blackout

  8. Radiological protection report 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Two years after the massive release of radiation from the nuclear power plants at Fukushima Dai-ichi, the repercussions continue to preoccupy the radiological and emergency protection community, both in Switzerland and internationally. In Switzerland the Swiss Federal Nuclear Safety Inspectorate (ENSI) has initiated measures as part of the European Union Stress Tests and has its own Fukushima Action Plan. In this Annual Report, ENSI focuses on radiological protection in Swiss nuclear facilities. The average individual dose has changed little compared with previous years. At 0.7 mSv, it is significantly below the limit both for persons exposed to radiation during their work (20 mSv) and the annual average rate of exposure for the population in Switzerland as a whole (5.5 mSv). In terms of collective doses, the extensive maintenance work at the Leibstadt power plant (KKL) resulted in a doubling of rates compared with recent years. However, in the remaining nuclear facilities the rates have not changed significantly. The highest individual dose during the year under review was 13 mSv. Exposure rates in 2012 for all those exposed to radiation during work in facilities subject to ENSI surveillance were below the maximum limit. Greater attention is now being given to work in high and variable radiation fields and in difficult conditions. Swiss nuclear facilities continue to operate a consistent radiological protection approach. Measuring equipment plays an important role in radiological protection. Having conducted a range of inspections and comparative measurements of aerosol-iodine filters and waste water sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable data. ENSI maintains a test laboratory that analyses samples from nuclear facilities and their immediate vicinity and also conducts field

  9. The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt

    International Nuclear Information System (INIS)

    2013-01-01

    Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, all NEA member countries took early action to ensure and confirm the continued safety of their nuclear power plants and the protection of the public. After these preliminary safety reviews, all countries with nuclear facilities carried out comprehensive safety reviews, often referred to as 'stress tests', which reassessed safety margins of nuclear facilities with a primary focus on challenges related to conditions experienced at the Fukushima Daiichi nuclear power plant, for example extreme external events and the loss of safety functions, or capabilities to cope with severe accidents. As appropriate, improvements are being made to safety and emergency response systems to ensure that nuclear power plants are capable of withstanding events that lead to loss of electrical power and/or cooling capability. In the weeks following the accident, the NEA immediately began establishing expert groups in the nuclear safety and radiological protection areas, as well as contributing to information exchange with the Japanese authorities and other international organisations. It promptly provided a forum for high-level decision makers and regulators within the G8-G20 frameworks. The NEA actions taken at the international level in response to the accident have been carried out primarily by the three NEA standing technical committees concerned with nuclear and radiation safety issues - the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH) - under the leadership of the CNRA. More than two years following the accident, the NEA continues to assist the Japanese authorities in dealing with their nuclear safety and recovery efforts as well as to facilitate international co-operation on nuclear safety and radiological protection matters. It is strongly supporting the establishment of

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

    International Nuclear Information System (INIS)

    2001-01-01

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

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

    International Nuclear Information System (INIS)

    2005-01-01

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

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

    International Nuclear Information System (INIS)

    2004-01-01

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

  13. Radiological emergency response - a functional approach

    International Nuclear Information System (INIS)

    Chowdhury, P.

    1998-01-01

    The state of Louisiana's radiological emergency response programme is based on the federal guidance 'Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants' (NUREG-0654, FEMA-REP-1 Rev. 1). Over the past 14 years, the planning and implementation of response capabilities became more organized and efficient; the training programme has strengthened considerably; co-ordination with all participating agencies has assumed a more co-operative role, and as a result, a fairly well integrated response planning has evolved. Recently, a more 'functional' approach is being adopted to maximize the programme's efficiency not only for nuclear power plant emergency response, but radiological emergency response as a whole. First, several broad-based 'components' are identified; clusters of 'nodes' are generated for each component; these 'nodes' may be divided into 'sub-nodes' which will contain some 'attributes'; 'relational bonds' among the 'attributes' will exist. When executed, the process begins and continues with the 'nodes' assuming a functional and dynamic role based on the nature and characteristics of the 'attributes'. The typical response based on stand-alone elements is thus eliminated, the overlapping of functions is avoided, and a well structured and efficient organization is produced, that is essential for today's complex nature of emergency response. (author)

  14. Radioactivity level of soil around Baqiao coal-fired power plant in China

    International Nuclear Information System (INIS)

    Lu, Xinwei; Zhao, Caifeng; Chen, Cancan; Liu, Wen

    2012-01-01

    Natural radioactivity level of soil around Baqiao coal-fired power plant in China was determined using gamma ray spectrometry. The concentrations of 226 Ra, 232 Th and 40 K in the studied soil samples range from 27.6 to 48.8, 44.4 to 61.4 and 640.2 to 992.2 Bq kg −1 with an average of 36.1, 51.1 and 733.9 Bq kg −1 , respectively, which are slightly higher than the average values of Shaanxi soil. The radium equivalent activity, the air absorbed dose rate and the annual effective dose rate were calculated and compared with the internationally reported or reference values. The radium equivalent activities of the studied samples are below the internationally accepted values. The air absorbed dose rate and the annual effective dose rate received by the local residents due to the natural radionuclides in soil are slightly higher than the mean value of Xi'an and worldwide. - Highlights: ► Natural radioactivity in soil around the coal-fired power plant was determined. ► Radiological parameters were used to assess radiation hazard. ► The coal-fired power plant has affected the local radioactivity level.

  15. Off-shore nuclear power plant

    International Nuclear Information System (INIS)

    Nakanishi, T.

    1980-01-01

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

  16. Solar thermal power plants

    International Nuclear Information System (INIS)

    Schnatbaum, L.

    2009-01-01

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

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

    International Nuclear Information System (INIS)

    Bursik, A.

    2005-01-01

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

  18. Nuclear power plant remote monitoring system of Hessen (KFUe Hessen) now fully available

    International Nuclear Information System (INIS)

    Lettmann, W.; Merkel, M.

    1991-01-01

    The remote monitoring system for the Biblis nuclear power station has commenced operation in 1990. It is intended to provide the radiological data and other information required by the supervisory Land authority for performing its supervisory functions in accordance with the Atomic Energy Act. The monitoring station records and reports emissions of the reactor station during specified normal operation and as a result of incidents or accidents, measures local dose rates at four measuring stations at the power plant fence, and records the meteorological conditions. The system is explained in detail, including illustration and graphs. (BBR) [de

  19. Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities

    International Nuclear Information System (INIS)

    Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E.; Martin, N.

    2008-01-01

    The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys

  20. Alternative off-site power supply improves nuclear power plant safety

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  1. Review of the safety concept for fusion reactor concepts and transferability of the nuclear fission regulation to potential fusion power plants

    Energy Technology Data Exchange (ETDEWEB)

    Raeder, Juergen; Weller, Arthur; Wolf, Robert [Max-Planck-Institut fuer Plasmaphysik (IPP), Garching (Germany); Jin, Xue Zhou; Boccaccini, Lorenzo V.; Stieglitz, Robert; Carloni, Dario [Karlsruher Institute fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany); Pistner, Christoph [Oeko-Institut e.V., Darmstadt (Germany); Herb, Joachim [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany)

    2016-01-15

    This paper summarizes the current state of the art in science and technology of the safety concept for future fusion power plants (FPPs) and examines the transferability of the current nuclear fission regulation to the concepts of future fusion power plants. At the moment there exist only conceptual designs of future fusion power plants. The most detailed concepts with regards to safety aspects were found in the European Power Plant Conceptual Study (PPCS). The plant concepts discussed in the PPCS are based on magnetic confinement of the plasma. The safety concept of fusion power plants, which has been developed during the last decades, is based on the safety concepts of installations with radioactive inventories, especially nuclear fission power plants. It applies the concept of defence in depth. However, there are specific differences between the implementations of the safety concepts due to the physical and technological characteristics of fusion and fission. It is analysed whether for fusion a safety concept is required comparable to the one of fission. For this the consequences of a purely hypothetical release of large amounts of the radioactive inventory of a fusion power plant and a fission power plant are compared. In such an event the evacuation criterion outside the plant is exceeded by several orders of magnitude for a fission power plant. For a fusion power plant the expected radiological consequences are of the order of the evacuation criterion. Therefore, a safety concept is also necessary for fusion to guarantee the confinement of the radioactive inventory. The comparison between the safety concepts for fusion and fission shows that the fundamental safety function ''confinement of the radioactive materials'' can be transferred directly in a methodical way. For a fusion power plant this fundamental safety function is based on both, physical barriers as well as on active retention functions. After the termination of the fusion

  2. Control of power plants and power systems. Proceedings

    International Nuclear Information System (INIS)

    Canales-Ruiz, R.

    1996-01-01

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

  3. Application of probabilistic safety goals to regulation of nuclear power plants in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Rzentkowski, G.; Akl, Y.; Yalaoui, S. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

    2013-07-01

    In the Canadian nuclear regulatory framework, Safety Goals are formulated in addition to the deterministic design requirements and the dose acceptance criteria so that risk to the public that originates from accidents outside the design basis is considered. In principle, application of the Safety Goals ensures that the likelihood of accidents with serious radiological consequences is extremely low, and the potential radiological consequences from severe accidents are limited as far as practicable. Effectively, the Safety Goals extend the plant design envelope to include not only the capabilities of the plant to successfully cope with various plant states, but also practical measures to halt the progression of severe accidents. This paper describes the general approach to the development of the Safety Goals and their application to the existing nuclear power plants in Canada. This general approach is consistent with the currently accepted international practice and Canadian regulatory experience. The results of probabilistic safety assessments indicate that the Safety Goals meet or exceed international safety objectives due to effective implementation of the defence-in-depth principle in the reactor design and plant operation. At the same time, the application of the Safety Goals reveal that practicable measures exist to further enhance the overall level of reactor safety by focusing on severe accident prevention and mitigation. These measures are being currently implemented through refurbishment projects and feedback on operating experience. (author)

  4. Technology and costs for decommissioning the Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1986-05-01

    The study shows that, from the viewpoint of radiological safety, a nuclear power plant can be dismantled immediately after it has been shut down and the fuel has been removed, which is estimated to take about one year. Most of the equipment that will be used in decommissioning is already available and is used routinely in maintenance and rebuilding work at the nuclear power plants. Special equipment need only be developed for dismantlement of the reactor vessel and for demolishing of heavy concrete structures. The dismantling of a nuclear power plant can be accomplished in about five years, with an average labour force of about 200 men. The maximum labour force required for Ringhals 1 has been estimated at about 500 men during the first years, when active systems are being dismantled in a number of fronts in the plant. During the last years when the buildings are being demolished, approximately 50 men are required. In order to limit the labour requirement and the dose burden to the personnel, the material is taken out in as large pieces as possible. The cost of decommissioning a boiling water reactor (BWR) of the size of Ringhals 1 has been estimated to be about MSEK 540 in January 1986 prices, and for a pressurized water reactor (PWR, Ringhals 2) about MSEK 460. The cost for the other Swedish nuclear power plants lie in the range of MSEK 410-760. These are the direct cost for the decommissioning work, to which must be added the costs of transportation and disposal of the decommissioning waste, about 100 000 m/sup3/. These costs have been estimated to be about MSEK 600 for the 12 Swedish reactors. (author)

  5. Safety evaluation of the nuclear power plant at Cattenom

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    This is a systematic compilation of the material which was dealt with at the level of the German-French Commission (on questions of the safety of nuclear installations) in this discussions about the nuclear power plant at Cattenom. As a supplement to the report published already in 1982, the Commission has officially released its deliberation results on the subjects constructive safety measures, radiological effects, and precautions in case of an emergency. The allegations according to which the installation is wanting in safety are countered by the joint statement of the chairmen of GPR (Permanent Group on Reactors) and RSK (German Commission on Reactor Safety) of August 29, 1986. (HSCH) [de

  6. Selective application of revised source terms to operating nuclear power plants

    International Nuclear Information System (INIS)

    Moon, Joo Hyun; Song, Jae Hyuk; Lee, Young Wook; Ko, Hyun Seok; Kang, Chang Sun

    2001-01-01

    More than 30 years later since 1962 when TID-14844 was promulgated, there has been big change of the US NRC's regulatory position in using accident source terms for radiological assessment following a design basis accident (DBA). To replace the instantaneous source terms of TID-14844, the time-dependent source terms of NUREG-1465 was published in 1995. In the meantime, the radiological acceptance criteria for reactor site evaluation in 10 CFR Part 100 were also revised. In particular, the concept of total effective dose equivalent has been incorporated in accordance with the radiation protection standards set forth in revised 10 CFR Part 20. Subsequently, the publication of Regulatory Guide 1.183 and the revision of Standard Review Plan 15.0.1 followed in 2000, which provided the licensee of operating nuclear power reactor with the acceptable guidance of applying the revised source term. The guidance allowed the holder of an operating license issued prior to January 10, 1997 to voluntarily revise the accident source terms used in the radiological consequence analyses of DBA. Regarding to its type of application, there suggested full and selective applications, Whether it is full or selective, based upon the scope and nature of associated plant modifications being proposed, the actual application of the revised source terms to an operating plant is expected to give a large impact on its facility design basis. Considering scope and cost of the analyses required for licensing, selective application is seemed to be more appealing to an licensee of the operating plant rather than full application. In this paper, hence, the selective application methodology is reviewed and is actally applied to the assessment of offsite radiological consequence following a LOCA at Ulchin Unit 3 and 4, in order to identify and analyze the potential impacts due to application of revised source terms and to assess the considerations taken in each application prior to its actual

  7. New threats and new challenges for radiological decision support

    DEFF Research Database (Denmark)

    Andersson, Kasper Grann; Astrup, Poul; Mikkelsen, Torben

    2011-01-01

    It is described how ongoing work will extend European standard decision support systems currently integrated in the nuclear power plant preparedness in many countries, to enable estimation of the radiological consequences of atmospheric dispersion of contaminants following a terror attack in a city....... Factors relating to the contaminant release processes, dispersion, deposition and post deposition migration are discussed, and non-radiological issues are highlighted in relation to decision making....

  8. Proposal for implementation of alternative source term in the nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Bazan L, A.; Lopez L, M.; Vargas A, A.; Cardenas J, J. B.

    2009-10-01

    In 2010 the nuclear power plant of Laguna Verde will implement the extended power upbeat in both units of the plant. Agree with methodology of NEDC-33004P-A, (constant pressure power up rate), and the source term of core, for accidents evaluations, were increased in proportion to the ratio of power level. This means that for the case of a design basis accident of loss of coolant an increase of power of 15% originated an increase of 15% in dose to main control room. Using the method of NEDC-33004P-A to extended power upbeat conditions was determined that the dose value to main control room is very near to regulatory limit established by SRP 6.4. By the above and in order to recover the margin, the nuclear power plant of Laguna Verde will calculate an alternative source term following the criteria established in RG 1.183 (alternative radiological source term for evaluating DBA at nuclear power reactor). This approach also have a more realistic dose value using the criterion of 10-CFR-50.67, in addition is predicted to get the benefit of additional operational flexibilities. This paper present the proposal of implementing the alternative source term in Laguna Verde. (Author)

  9. Environmental release targets for fusion power plants

    International Nuclear Information System (INIS)

    Gulden, W.; Raskob, W.

    2005-01-01

    Within the European fission community, so called European Utility Requirements were developed to define common targets, criteria and evaluation methods for, amongst others, safety, environmental protection and public health with respect to future nuclear fission power plant development. In the case of severe accidents, the objective is to restrict the radiological consequences to the vicinity of the plant, i.e., to avoid early and late countermeasures such as evacuation or relocation of the population, and to restrict food banning to small areas and the first year after the accident. Within the European Fusion Technology Programme, a methodology is being developed in compliance with these European Utility Requirements, to define design requirements for future fusion reactors. First results are presented. Concerning food banning, calculations revealed extremely conservative values for tritium in EU regulations and recommendations. This does not affect assessments for fission reactors, but is an overestimation of the tritium dose impact from ingestion. Therefore, in compliance with scientific justification, considerably higher maximum permissible activity levels for tritium should be considered

  10. Industrial safety in power plants

    International Nuclear Information System (INIS)

    1987-01-01

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

  11. NUCLEAR POWER PLANT

    Science.gov (United States)

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

    1963-05-14

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

  12. Nuclear and energy. Special issue on the Fukushima power plant

    International Nuclear Information System (INIS)

    2011-01-01

    This issue analyses the first consequences of the Fukushima accident at the world level, i.e. impacts which are either already noticeable or predictable. A first article proposes a portrait of Japan (its historical relationship with nature, the cultural education, the role of its bureaucracy, the Japanese business and political worlds) and evokes the nuclear safety organization at the institutional level. It also evokes the different companies involved in nuclear energy production. The second article discusses and comments the environmental and radiological impact of the accident (protection of the inhabitants, environment monitoring, comparison with Chernobyl, main steps of degradation of the reactors, releases in the sea, total release assessment, soil contamination, food contamination, radiation protection). A third article discusses the international impact, notably for the existing or projected power plants in different countries, in terms of public opinion, and with respect to negotiations on climate. The fourth article discusses the reactions of different countries possessing nuclear reactors. The last article questions the replacement of the lost production (that of Fukushima and maybe another power plant) by renewable energies

  13. Estimation of radiological consequences from accidental iodine releases at nuclear power plants

    International Nuclear Information System (INIS)

    Drozdovich, V.V.

    2000-01-01

    To evaluate the radiological consequences of a beyond design-basis accident at an NPP for a WWER-1000 reactor, a preliminary investigation was conducted. The scenario of the hypothetical accident was a fast loss of coolant as a result of a rupture in the primary circuit pipeline with diameter of 850 mm and minimum radiation consequences when containment integrity is preserved. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Using modem knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways: (a) extemal exposure from radionuclides in air; (b) extemal exposure from radionuclides deposited on the ground surface; (c) internal exposures from inhalation of radionuclides in air; and (d) internal exposure from ingestion of radionuclides with contaminated foodstuffs. Risk was estimated for populations living at different distances from the source. Preliminary results show that the methodology and models can be applied to the evaluation of radiological danger of an accident at an NPP. Experience from the Chernobyl accident has shown that the damage from a radiation accident can be vast. Expenditures on advanced simulations of the different accident scenarios are worth the cost because they allow radiation protection of populations for these low probability cases, but nevertheless possible accidents at an NPP. (authors)

  14. Nuclear power. Volume 1. Nuclear power plant design

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

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

  15. Naturally occurring radioactive materials (NORMs) generated from lignite-fired power plants in Kosovo

    International Nuclear Information System (INIS)

    Hasani, F.; Shala, F.; Xhixha, G.; Xhixha, M.K.; Hodolli, G.; Kadiri, S.; Bylyku, E.; Cfarku, F.

    2014-01-01

    The energy production in Kosovo depends primarily on lignite-fired power plants. During coal combustion, huge amounts of fly ash and bottom ash are generated, which may result in enriched natural radionuclides; therefore, these radionuclides need to be investigated to identify the possible processes that may lead to the radiological exposure of workers and the local population. Lignite samples and NORMs of fly ash and bottom ash generated in lignite-fired power plants in Kosovo are analyzed using a gamma-ray spectrometry method for the activity concentration of natural radionuclides. The average activity concentrations of 40 K, 226 Ra and 232 Th in lignite are found to be 36 ± 8 Bq kg −1 , 9 ± 1 Bq kg −1 and 9 ± 3 Bq kg −1 , respectively. Indications on the occurrence and geochemical behavior of uranium in the lignite matrix are suggested. The activity concentrations of natural radionuclides in fly ash and bottom ash samples are found to be concentrated from 3 to 5 times that of the feeding lignite. The external gamma-ray absorbed dose rate and the activity concentration index are calculated to assess the radiological hazard arising from ash disposal and recycling in the cement industry. - Highlights: • NORMs in lignite combustion residues from CFPPs are studied. • Th/U indicates either low U uptake from host rocks and/or high leaching from peat. • The concentration factor of NORMs in fly and bottom ash samples are 3–5 times. • No 226 Ra enrichment is observed in fly ash while a depletion in bottom ash. • The reuse of fly ash in cement industry poses no significant radiological issue

  16. Health care during reactor shut down for maintenance, inspection and repair of nuclear power plants in the Netherlands

    International Nuclear Information System (INIS)

    Wijker, H.

    1975-01-01

    The health care for workers in power plants has medical-biological aspects and physical-technical ones. It requires a close collaboration between the medical doctor and the health physicist. A combination of prevention, supervision and checks provides an optimumhealth care. It includes plant design, medical examination, whole body counting, radiological passports, dose reserve calculations, dose measurements, radiation supervision services, physical and medical checks. The discussion of the subjects comprises organization and experience in the Netherlands

  17. Power plants 2010. Lectures

    International Nuclear Information System (INIS)

    2010-01-01

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

  18. The year 2000 power plant

    International Nuclear Information System (INIS)

    Roman, H.T.

    1989-01-01

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

  19. The United States Federal Monitoring and Assessment Centre and radiological database management

    International Nuclear Information System (INIS)

    Mueller, P.G.

    1998-01-01

    In the spring of 1979, a series of events occurring at the Three Mile Island Nuclear Power plant near Harrisburg, Pennsylvania, resulted in severe core damage. Recognizing that state resources were insufficient to respond to the first major nuclear power plant emergency in the United States, the State of Pennsylvania asked the Federal Government for assistance. The United States Government undertook the preparation of a plan, which would co-ordinate all federal assets. The Federal Radiological Emergency Response Plan (FRERP) assigned unique responsibilities and authorities for responding to domestic radiological emergencies to each of 12 different federal agencies which form the FRERP. The overall data collection, analysis, and processing procedures within the FRMAC are overviewed. (author)

  20. Radiological health effects models for nuclear power plant accident consequence analysis

    International Nuclear Information System (INIS)

    Evans, J.S.; Moeller, D.W.

    1989-01-01

    Improved health effects models have been developed for assessing the early effects, late somatic effects and genetic effects that might result from low-LET radiation exposures to populations following a major accident in a nuclear power plant. All the models have been developed in such a way that the dynamics of population risks can be analyzed. Estimates of life years lost and the duration of illnesses were generated and a framework recommended for summarizing health impacts. Uncertainty is addressed by providing models for upper, central and lower estimates of most effects. The models are believed to be a significant improvement over the models used in the U.S. Nuclear Regulatory Commission's Reactor Safety Study, and they can easily be modified to reflect advances in scientific understanding of the health effects of ionizing radiation

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  2. Organization patterns of PWR power plants

    International Nuclear Information System (INIS)

    Leicman, J.

    1980-01-01

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

  3. Nuclear power plant siting

    International Nuclear Information System (INIS)

    Sulkiewicz, M.; Navratil, J.

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

  4. Reliability analysis of meteorological data registered during nuclear power plant normal operation

    International Nuclear Information System (INIS)

    Amado, V.; Ulke, A.; Marino, B.; Thomas, L.

    2011-01-01

    The atmosphere is the environment in which gaseous radioactive discharges from nuclear power plants are transported. It is therefore essential to have reliable meteorological information to characterize the dispersion and feed evaluation models and radiological environmental impact during normal operation of the plant as well as accidental releases. In this way it is possible to determine the effects on the environment and in humans. The basic data needed to represent adequately the local weather include air temperature, wind speed and direction, rainfall, humidity and pressure. On the other hand, specific data consistent with the used model is required to determine the turbulence, for instance, radiation, cloud cover and vertical temperature gradient. It is important that the recorded data are representative of the local meteorology. This requires, first, properly placed instruments, that should be kept in operation and undergoing maintenance on a regular basis. Second, but equally substantial, a thorough analysis of its reliability must be performed prior to storage and/or data processing. In this paper we present the main criteria to consider choosing the location of a meteorological tower in the area of a nuclear power plant and propose a methodology for assessing the reliability of recorded data. The methodology was developed from the analysis of meteorological data registered in nuclear power plants in Argentina. (authors) [es

  5. Annual radiological environmental operating report: Browns Ferry Nuclear Plant, 1992

    International Nuclear Information System (INIS)

    1993-04-01

    This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public

  6. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

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

  7. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

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

  8. State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

    International Nuclear Information System (INIS)

    1980-04-01

    A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report

  9. Wind power plant system services

    DEFF Research Database (Denmark)

    Basit, Abdul; Altin, Müfit

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

  10. Naturally occurring radioactive materials (NORMs) generated from lignite-fired power plants in Kosovo.

    Science.gov (United States)

    Hasani, F; Shala, F; Xhixha, G; Xhixha, M K; Hodolli, G; Kadiri, S; Bylyku, E; Cfarku, F

    2014-12-01

    The energy production in Kosovo depends primarily on lignite-fired power plants. During coal combustion, huge amounts of fly ash and bottom ash are generated, which may result in enriched natural radionuclides; therefore, these radionuclides need to be investigated to identify the possible processes that may lead to the radiological exposure of workers and the local population. Lignite samples and NORMs of fly ash and bottom ash generated in lignite-fired power plants in Kosovo are analyzed using a gamma-ray spectrometry method for the activity concentration of natural radionuclides. The average activity concentrations of (40)K, (226)Ra and (232)Th in lignite are found to be 36 ± 8 Bq kg(-1), 9 ± 1 Bq kg(-1) and 9 ± 3 Bq kg(-1), respectively. Indications on the occurrence and geochemical behavior of uranium in the lignite matrix are suggested. The activity concentrations of natural radionuclides in fly ash and bottom ash samples are found to be concentrated from 3 to 5 times that of the feeding lignite. The external gamma-ray absorbed dose rate and the activity concentration index are calculated to assess the radiological hazard arising from ash disposal and recycling in the cement industry. Copyright © 2014 Elsevier Ltd. All rights reserved.

  11. Annual radiological environmental monitoring report, Watts Bar Nuclear Plant

    International Nuclear Information System (INIS)

    1988-05-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1988. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. The exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment. 4 refs., 2 figs., 1 tab

  12. Radiological impact from spanish coal power plants.2.- Dispersion model for deconcentration calculations

    International Nuclear Information System (INIS)

    Alvarez, M.C.; Garzon, L.

    1990-01-01

    In this paper a practical dispersion model is presented, which permits to calculate, in Spain, the concentration of natural radionuclides released to the atmosphere from coal power plants. To apply the model it is necessary to know the following data: emission rates, dry deposition velocity, scavenging coefficient, mixing layer height, together with climatological frequency data relating to wind speed and wind direction (to determinate trajectories from a given source) in the areas examined. Meteorological data can be obtained from meteorological stations across Spain. (Author)

  13. Images of nuclear power plants

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  14. On nuclear power plant uprating

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  15. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    Energy Technology Data Exchange (ETDEWEB)

    Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Semova, T; Bonchev, Ts [Sofia Univ. (Bulgaria). Fizicheski Fakultet

    1996-12-31

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs.

  16. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    International Nuclear Information System (INIS)

    Angelov, V.; Semova, T.; Bonchev, Ts.

    1995-01-01

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs

  17. Small hydroelectric power plants

    International Nuclear Information System (INIS)

    Helgesen, Boerre

    2002-01-01

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

  18. The Kuroshio power plant

    CERN Document Server

    Chen, Falin

    2013-01-01

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

  19. Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1991

    International Nuclear Information System (INIS)

    1992-04-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1991. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment a a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment

  20. Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992

    International Nuclear Information System (INIS)

    1993-04-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment

  1. Security aspects and radiological protection analyzed in the Semi-industrial irradiation plant in Peru

    International Nuclear Information System (INIS)

    Del Valle O, C.

    1996-01-01

    The safety aspects and the radiological protection analyzed on regular and emergency operation of a multipurpose irradiation plant PIMU are shown. All its design requirements are described following a strict safety philosophy. The plant is classified into the generic category IV for storage in pool panoramic irradiators. This paper studies every aspect related to a safety operation of the gamma's facility, PIMU, being used as reference in order to obtain the corresponding licensing. Aspects related to the regular and safety operation of the whole plant are taken into account, so all the possible emergency cases and their respective answers will be known, analyzing cases and causes of accidents, as well as references to the program of radiological protection. Registers and documents are written in order to be used at the plant, all the lineament for the development of a good preventive and corrective maintenance are given, observing all the necessary adjustments. A list of the principal examinations of the technical condition of the plant is presented. (author). 2 refs

  2. Guidelines for training and qualification of radiological protection technicians

    International Nuclear Information System (INIS)

    1987-08-01

    These guidelines, used in combination with plant-specific job analysis, provide the framework for a training and qualification program for radiological protection technicians at nuclear power plants. Radiological protection technicians are defined as those individuals, both plant and contractor, who will be engaged in the evaluation of radiological conditions in the nuclear plant and the implementation of the necessary radiological safety measures as they apply to nuclear plant workers and members of the general public. An important aspect of this work is recognizing and handling unusual situations involving radioactivity, including incidents related to degraded core conditions. These guidelines incorporate the results of an industry-wide job analysis and task analysis (JTA) combined with industry operating experience review. However, the industry-wide analyses did not identify all important academic and fundamental knowledge and skills. Further in-depth analysis by subject matter experts produced additional knowledge and skills that were added to these guidelines. All utilities should use these guidelines in conjunction with plant-specific and industry-wide JTA results to develop or validate their radiological protection technician training program. Plant-specific information should be used to establish appropriate training program content. This plant-specific information should reflect unique job duties, equipment, operating experience, and trainee entry-level qualifications. Revisions to these guidelines should be reviewed for applicability and incorporated into the training program using each utility's training system development (TSD) procedures. Plant-specific job analysis and task analysis data is essential to the development of performance-based training programs. These analyses are particularly useful in selecting tasks for training and in developing on-the-job training (OJT), laboratory training, and mock-up training. Qualification programs based on these

  3. Radiological surveillance in Mexico, derived of the accident of the Fukushima Daiichi nuclear power plant; Vigilancia radiologica en Mexico, derivado del accidente en la central nuclear de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    Aguirre G, J.; Nohpal J, X., E-mail: jaguirre@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Departamento de Vigilancia Radiologica, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    March 11, 2011 an earthquake of 9.0 grades in the Richter scale, originated in the coast of Tohoku, Japan, in the Pacific Ocean gave origin to a tsunami that caused an accident in the Fukushima Daiichi nuclear power plant. Due to this accident, derived of the loss of the reactor cooling system, as well as of the prolonged absence of alternating and direct current, radiological protection actions were realized without being able to avoid the liberation of radioactive material to the atmosphere and ocean. The radiological impact of these liberations, not only in Japan but around the world, mainly in the north hemisphere of the Earth, was analyzed by means of environmental dose measurements and radionuclide concentrations in soil and water, among others. In the Mexico case, air samples data were obtained, as well as environmental dose celerity and full-length counts of the people coming from Japan near the disaster area. The present work contains the obtained results of the realized measurements in Mexico, same that have been used to make a summary and analysis of the dispersion in the environment in several countries of the world. (Author)

  4. Economics of hybrid photovoltaic power plants

    Energy Technology Data Exchange (ETDEWEB)

    Breyer, Christian

    2012-08-16

    The global power supply stability is faced to several severe and fundamental threats, in particular steadily increasing power demand, diminishing and degrading fossil and nuclear energy resources, very harmful greenhouse gas emissions, significant energy injustice and a structurally misbalanced ecological footprint. Photovoltaic (PV) power systems are analysed in various aspects focusing on economic and technical considerations of supplemental and substitutional power supply to the constraint conventional power system. To infer the most relevant system approach for PV power plants several solar resources available for PV systems are compared. By combining the different solar resources and respective economics, two major PV systems are identified to be very competitive in almost all regions in the world. The experience curve concept is used as a key technique for the development of scenario assumptions on economic projections for the decade of the 2010s. Main drivers for cost reductions in PV systems are learning and production growth rate, thus several relevant aspects are discussed such as research and development investments, technical PV market potential, different PV technologies and the energetic sustainability of PV. Three major market segments for PV systems are identified: off-grid PV solutions, decentralised small scale on-grid PV systems (several kWp) and large scale PV power plants (tens of MWp). Mainly by application of 'grid-parity' and 'fuel-parity' concepts per country, local market and conventional power plant basis, the global economic market potential for all major PV system segments is derived. PV power plant hybridization potential of all relevant power technologies and the global power plant structure are analyzed regarding technical, economical and geographical feasibility. Key success criteria for hybrid PV power plants are discussed and comprehensively analysed for all adequate power plant technologies, i.e. oil, gas and coal fired power

  5. Economics of hybrid photovoltaic power plants

    Energy Technology Data Exchange (ETDEWEB)

    Breyer, Christian

    2012-08-16

    The global power supply stability is faced to several severe and fundamental threats, in particular steadily increasing power demand, diminishing and degrading fossil and nuclear energy resources, very harmful greenhouse gas emissions, significant energy injustice and a structurally misbalanced ecological footprint. Photovoltaic (PV) power systems are analysed in various aspects focusing on economic and technical considerations of supplemental and substitutional power supply to the constraint conventional power system. To infer the most relevant system approach for PV power plants several solar resources available for PV systems are compared. By combining the different solar resources and respective economics, two major PV systems are identified to be very competitive in almost all regions in the world. The experience curve concept is used as a key technique for the development of scenario assumptions on economic projections for the decade of the 2010s. Main drivers for cost reductions in PV systems are learning and production growth rate, thus several relevant aspects are discussed such as research and development investments, technical PV market potential, different PV technologies and the energetic sustainability of PV. Three major market segments for PV systems are identified: off-grid PV solutions, decentralised small scale on-grid PV systems (several kWp) and large scale PV power plants (tens of MWp). Mainly by application of 'grid-parity' and 'fuel-parity' concepts per country, local market and conventional power plant basis, the global economic market potential for all major PV system segments is derived. PV power plant hybridization potential of all relevant power technologies and the global power plant structure are analyzed regarding technical, economical and geographical feasibility. Key success criteria for hybrid PV power plants are discussed and comprehensively analysed for all adequate power plant technologies, i.e. oil, gas and

  6. 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)

  7. Developing new methodology for nuclear power plants vulnerability assessment

    International Nuclear Information System (INIS)

    Kostadinov, Venceslav

    2011-01-01

    Research highlights: → Paper presents new methodology for vulnerability assessment of nuclear power plants. → First universal quantitative risks assessment model for terrorist attack on a NPPs. → New model enhance security, reliability and safe operation of all energy infrastructure. → Significant research benefits: increased NPPs security, reliability and availability. → Useful new tool for PRA application to evaluation of terrorist threats on NPPs. - Abstract: The fundamental aim of an efficient regulatory emergency preparedness and response system is to provide sustained emergency readiness and to prevent emergency situations and accidents. But when an event occurs, the regulatory mission is to mitigate consequences and to protect people and the environment against nuclear and radiological damage. The regulatory emergency response system, which would be activated in the case of a nuclear and/or radiological emergency and release of radioactivity to the environment, is an important element of a comprehensive national regulatory system of nuclear and radiation safety. In the past, national emergency systems explicitly did not include vulnerability assessments of the critical nuclear infrastructure as an important part of a comprehensive preparedness framework. But after the huge terrorist attack on 11/09/2001, decision-makers became aware that critical nuclear infrastructure could also be an attractive target to terrorism, with the purpose of using the physical and radioactive properties of the nuclear material to cause mass casualties, property damage, and detrimental economic and/or environmental impacts. The necessity to evaluate critical nuclear infrastructure vulnerability to threats like human errors, terrorist attacks and natural disasters, as well as preparation of emergency response plans with estimation of optimized costs, are of vital importance for assurance of safe nuclear facilities operation and national security. In this paper presented

  8. Some power uprate issues in nuclear power plants

    International Nuclear Information System (INIS)

    Tipping, Philip

    2008-01-01

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

  9. Offshore atomic power plants

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

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

  10. 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).

  11. Hybrid combined cycle power plant

    International Nuclear Information System (INIS)

    Veszely, K.

    2002-01-01

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

  12. Calculation of risk-based detection limits for radionuclides in the liquid effluents from Korean nuclear power plants

    International Nuclear Information System (INIS)

    Cheong, Jae Hak

    2017-01-01

    In order to review if present detection limits of radionuclides in liquid effluent from nuclear power plants are effective enough to warrant compliance with regulatory discharge limits, a risk-based approach is developed to derive a new detection limit for each radionuclide based on radiological criteria. Equations and adjustment factors are also proposed to discriminate the validity of the detection limits for multiple radionuclides in the liquid effluent with or without consideration of the nuclide composition. From case studies to three nuclear power plants in Korea with actual operation data from 2006 to 2015, the present detection limits have turned out to be effective for Hanul Unit 1 but may not be sensitive enough for Kori Unit 1 (8 out of 14 radionuclides) and Wolsong Unit 1 (9 out of 42 radionuclides). However, it is shown that the present detection limits for the latter two nuclear power plants can be justified, if credit is given to the radionuclide composition. Otherwise, consideration should be given to adjustment of the present detection limits. The risk-based approach of this study can be used to determine the validity of established detection limits of a specific nuclear power plant. (author)

  13. 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.)

  14. Evolution of radiation protection of overall decommissioning and Dismantling of a Nuclear Power Plants

    International Nuclear Information System (INIS)

    Ortiz, M. T.; Ondaro, M.; Irun, I.; Just, J.

    2000-01-01

    From the point of view of Radiological Protection, the overall Decommissioning and Dismantling (D and D) Plan of a Nuclear Power Plant cannot be considered in isolation without considering the evolution of the radiological characteristics of the installation and the site itself from previous, during and final states. This experience of D and D is the first in Spain and in other European countries due to several aspects: 1) the reference reactor technology, 2) total grass power, and 3) management of a great amount of materials to be released. Three decommissioning alternatives were studied: Indefinite maintenance in shutdown state, Stage 1. Stage 2 for the defuelled reactor vessel and contents, with decontamination of most of the rest of the site. Immediate dismantling to Stage 3. Stage 2 was the alternative selected with the release of 80% of the site, keeping the remaining 20% of the site as a regulated area, housing the reactor vessel in a new structure and removing the radioactive waste. The above, along with the fact that this is a specific type of natural uranium-graphite-gas plant (NUGG) and that ownership of the facility has been transferred for dismantling (from HIFRENSA to ENRESA), implies a series of preliminary considerations that, for the purposes of this article, are compiled in the following aspects: a) Preliminary phase prior to transfer, b) Preparatory phase, and c) Dismantling phase. This paper describes aspects under the D and D experiences at CN-V1 NPP, now in progress, from the point of view of the radiological aspects in relation with the continuous updating of the source term. Operative Radiological nuclide vectors, applicable in the Radiation Protection tasks, are also commented to prevent and evaluate several risks during the execution of the works. Finally, there is a description of the results obtained from the work performed to decay the three actual nuclide vectors, to evaluate and obtain activity calculations for the release of the

  15. Fatigue evaluation of socket welded piping in nuclear power plant

    International Nuclear Information System (INIS)

    Vecchio, R.S.

    1996-01-01

    Fatigue failures in piping systems occur, almost without exception, at the welded connections. In nuclear power plant systems, such failures occur predominantly at the socket welds of small diameter piping ad fillet attachment welds under high-cycle vibratory conditions. Nearly all socket weld fatigue failures are identified by leaks which, though not high in volume, generally are costly due to attendant radiological contamination. Such fatigue cracking was recently identified in the 3/4 in. diameter recirculation and relief piping socket welds from the reactor coolant system (RCS) charging pumps at a nuclear power plant. Consequently, a fatigue evaluation was performed to determine the cause of cracking and provide an acceptable repair. Socket weld fatigue life was evaluated using S-N type fatigue life curves for welded structures developed by AASHTO and the assessment of an effective cyclic stress range adjacent to each socket weld. Based on the calculated effective tress ranges and assignment of the socket weld details to the appropriate AASHTO S-N curves, the socket weld fatigue lives were calculated and found to be in excellent agreement with the accumulated cyclic life to-date

  16. Power generation by nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.

    2004-01-01

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

  17. 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.)

  18. Radiological protection report 2012; Strahlenschutzbericht 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    Two years after the massive release of radiation from the nuclear power plants at Fukushima Dai-ichi, the repercussions continue to preoccupy the radiological and emergency protection community, both in Switzerland and internationally. In Switzerland the Swiss Federal Nuclear Safety Inspectorate (ENSI) has initiated measures as part of the European Union Stress Tests and has its own Fukushima Action Plan. In this Annual Report, ENSI focuses on radiological protection in Swiss nuclear facilities. The average individual dose has changed little compared with previous years. At 0.7 mSv, it is significantly below the limit both for persons exposed to radiation during their work (20 mSv) and the annual average rate of exposure for the population in Switzerland as a whole (5.5 mSv). In terms of collective doses, the extensive maintenance work at the Leibstadt power plant (KKL) resulted in a doubling of rates compared with recent years. However, in the remaining nuclear facilities the rates have not changed significantly. The highest individual dose during the year under review was 13 mSv. Exposure rates in 2012 for all those exposed to radiation during work in facilities subject to ENSI surveillance were below the maximum limit. Greater attention is now being given to work in high and variable radiation fields and in difficult conditions. Swiss nuclear facilities continue to operate a consistent radiological protection approach. Measuring equipment plays an important role in radiological protection. Having conducted a range of inspections and comparative measurements of aerosol-iodine filters and waste water sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable data. ENSI maintains a test laboratory that analyses samples from nuclear facilities and their immediate vicinity and also conducts field

  19. Perspectives of nuclear power plants

    International Nuclear Information System (INIS)

    Vajda, Gy.

    2001-01-01

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

  20. Upgrading radiological work practices through employee participation

    International Nuclear Information System (INIS)

    Beckman, W.L.

    1988-01-01

    Following the shutdown of the Midland Plant in 1984, Consumers Power Company found itself with a need to reorganize its nuclear operations department. The reorganization took place in November 1984. At that time the plant was just completing an intermittent outage that had begun in September 1983. Over the previous 2 yr, the plant had expended 1,500 person-rem and generated 1330 m 3 of radioactive waste. In addition, an overexposure and a shipping violation in early 1984 had contributed to a deteriorating regulatory picture for radiological services. In an attempt to understand the problem confronting the plant, the new organization set up a group of meetings for each department to identify their barriers to becoming a high-performance organization. These meetings, which became known as barrier meetings, were used to identify barriers to performance, such as overly restrictive requirements, excessive paperwork, facility limitations, and improper job assignments. Following the barrier meetings, corrective actions and individuals responsible for completing these actions were identified. Most recent efforts have been in upgrading radiological work practices

  1. Problems of power plant capital demands

    International Nuclear Information System (INIS)

    Slechta, V.; Bohal, L.

    1986-01-01

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

  2. Nuclear power plant diagnostic system

    International Nuclear Information System (INIS)

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  3. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    Energy Technology Data Exchange (ETDEWEB)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs.

  4. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    International Nuclear Information System (INIS)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs

  5. Topics to be covered in safety analysis reports for nuclear power plants with pressurized water reactors or boiling water reactors in the F.R.G

    International Nuclear Information System (INIS)

    Kohler, H.A.G.

    1977-01-01

    This manual aims at defining the standards to be used in Safety Analysis Reports for Nuclear Power Plants with Pressurized Water Reactors or Boiling Water Reactors in the Federal Republic of Germany. The topics to be covered are: Information about the site (geographic situation, settlement, industrial and military facilities, transport and communications, meteorological conditions, geological, hydrological and seismic conditions, radiological background), description of the power plant (building structures, safety vessel, reactor core, cooling system, ventilation systems, steam power plant, electrical facilities, systems for measurement and control), indication of operation (commissioning, operation, safety measures, radiation monitoring, organization), incident analysis (reactivity incidents, loss-of-coolant incidents, external impacts). (HP) [de

  6. Next Generation Geothermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-09-01

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

  7. Power plant chemical technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

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

  8. Advanced plant design recommendations from Cook Nuclear Plant experience

    International Nuclear Information System (INIS)

    Zimmerman, W.L.

    1993-01-01

    A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

  9. Nuclear power plants in populated areas

    International Nuclear Information System (INIS)

    Wachsmann, F.

    1973-01-01

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

  10. Vital area identification software VIP for the physical protection of nuclear power plants

    International Nuclear Information System (INIS)

    Jung, Woo Sik; Park, Chang Kue; Yang, Joon Eon

    2004-01-01

    There are two major factors to be considered for the physical protection of nuclear power plants. They are a design basis threat (DBT) and the vital area identification (VAI). The DBT has been considered as 'the maximum credible threat.' The vital area is defined as 'an area inside a protected area containing equipment, systems or devices, or nuclear materials, the sabotage of which could directly or indirectly lead to unacceptable radiological consequences.' For the VAI of nuclear power plants, a software VIP (Vital area Identification Package based on PSA method) is being developed. The VIP is based on the current probabilistic safety assessment (PSA) techniques. The PSA method, including internal as well as external events, is known as the most complete and consistent method for identifying various accident sequences that might result in a core melt and radioactive material release to the environment. Thus, the VIP employs a fault tree analysis method in the PSA and utilizes the PSA results

  11. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    Franke, J.; Viefhues, D.

    1984-04-01

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

  13. Assuring the competence of nuclear power plant contractor personnel

    International Nuclear Information System (INIS)

    2001-07-01

    This report was prepared in response to a recommendation by the IAEA International Working Group on Training and Qualification of NPP Personnel (JWG-T and Q) and supported by a number of IAEA meetings on NPP personnel training. IAEA publications on NPP training are the only international documents available to all Member States with nuclear programmes. This report complements the following IAEA publications on NPP personnel training: Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook; IAEA-TECDOC-1057, Experience in the Use of Systematic Approach to Training (SAT) for Nuclear Power Plant Personnel and IAEA-TECDOC-1063, IAEA World Survey on Nuclear Power Plant Personnel Training. This TECDOC also supplements the IAEA Safety Guide 50-SG-O1 (Rev. 1), Staffing of Nuclear Power Plants and the Recruitment Training and Authorization of Operating Personnel and Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants. Operation. Within the context of this report NPP contractors are defined as any personnel working for a nuclear power plant who are not directly employed by the nuclear power plant. Competence is the ability to perform to identified standards; it comprises skills, knowledge and attitudes and may be developed through education, experience and training. Qualification is a formal statement of achievement, resulting from an auditable assessment; if competence is assessed, the qualification becomes a formal statement of competence and may be shown on a certificate, diploma, etc. It is recognized that personnel are used to perform tasks that are of a specialised or temporary nature where it is not feasible to hire or maintain a full-time NPP employee. Accordingly, contractors may be used in a variety of situations to support NPPs. Typical situations include: supplies and services being delivered by the contractors that are subject to different quality standards based on a graded approach to assuring

  14. Assuring the competence of nuclear power plant contractor personnel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report was prepared in response to a recommendation by the IAEA International Working Group on Training and Qualification of NPP Personnel (JWG-T and Q) and supported by a number of IAEA meetings on NPP personnel training. IAEA publications on NPP training are the only international documents available to all Member States with nuclear programmes. This report complements the following IAEA publications on NPP personnel training: Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook; IAEA-TECDOC-1057, Experience in the Use of Systematic Approach to Training (SAT) for Nuclear Power Plant Personnel and IAEA-TECDOC-1063, IAEA World Survey on Nuclear Power Plant Personnel Training. This TECDOC also supplements the IAEA Safety Guide 50-SG-O1 (Rev. 1), Staffing of Nuclear Power Plants and the Recruitment Training and Authorization of Operating Personnel and Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants. Operation. Within the context of this report NPP contractors are defined as any personnel working for a nuclear power plant who are not directly employed by the nuclear power plant. Competence is the ability to perform to identified standards; it comprises skills, knowledge and attitudes and may be developed through education, experience and training. Qualification is a formal statement of achievement, resulting from an auditable assessment; if competence is assessed, the qualification becomes a formal statement of competence and may be shown on a certificate, diploma, etc. It is recognized that personnel are used to perform tasks that are of a specialised or temporary nature where it is not feasible to hire or maintain a full-time NPP employee. Accordingly, contractors may be used in a variety of situations to support NPPs. Typical situations include: supplies and services being delivered by the contractors that are subject to different quality standards based on a graded approach to assuring

  15. Guidance for emergency planning in nuclear power plants

    International Nuclear Information System (INIS)

    Magnusson, Tommy; Ekdahl, Maria

    2008-06-01

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

  16. 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

  17. 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.

  18. 76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-01-10

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

  19. An aerial radiological survey of the Vermont Yankee Nuclear Power Station and surrounding area, Vernon, Vermont

    International Nuclear Information System (INIS)

    Reiman, R.; Bluitt, C.M.

    1993-10-01

    An aerial radiological survey was conducted over the Vermont Yankee Nuclear Power Station in Vernon, Vermont, during the period August 7 through August 17, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over a 65-square-mile (168-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Vermont Yankee Power Station and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based open-quotes benchmarkclose quotes exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

  20. An aerial radiological survey of the Yankee Rowe Nuclear Power Station and surrounding area, Rowe, Massachusetts

    International Nuclear Information System (INIS)

    Boyns, P.K.; Bluitt, C.M.

    1993-09-01

    An aerial radiological survey was conducted over the Yankee Rowe Nuclear Power Station in Rowe, Massachusetts, during the period August 17--24, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over an 87-square-mile (225-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Yankee Rowe Power Station and the surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based ''benchmark'' exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

  1. Radiological Environmental Protection for LCLS-II High Power Operation

    Science.gov (United States)

    Liu, James; Blaha, Jan; Cimeno, Maranda; Mao, Stan; Nicolas, Ludovic; Rokni, Sayed; Santana, Mario; Tran, Henry

    2017-09-01

    The LCLS-II superconducting electron accelerator at SLAC plans to operate at up to 4 GeV and 240 kW average power, which would create higher radiological impacts particularly near the beam loss points such as beam dumps and halo collimators. The main hazards to the public and environment include direct or skyshine radiation, effluent of radioactive air such as 13N, 15O and 41Ar, and activation of groundwater creating tritium. These hazards were evaluated using analytic methods and FLUKA Monte Carlo code. The controls (mainly extensive bulk shielding and local shielding around high loss points) and monitoring (neutron/photon detectors with detection capabilities below natural background at site boundary, site-wide radioactive air monitors, and groundwater wells) were designed to meet the U.S. DOE and EPA, as well as SLAC requirements. The radiological design and controls for the LCW systems [including concrete housing shielding for 15O and 11C circulating in LCW, 7Be and erosion/corrosion products (22Na, 54Mn, 60Co, 65Zn, etc.) captured in resin and filters, leak detection and containment of LCW with 3H and its waste water discharge; explosion from H2 build-up in surge tank and release of radionuclides] associated with the high power beam dumps are also presented.

  2. 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.)

  3. Hybrid wind-power-distillation plant

    Directory of Open Access Journals (Sweden)

    Ninić Neven

    2012-01-01

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

  4. Power plants 2009. Lectures

    International Nuclear Information System (INIS)

    2009-01-01

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

  5. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    International Nuclear Information System (INIS)

    Harris, P.W.

    2001-01-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  6. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Harris, P.W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

    2001-07-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  7. Annual radiological environmental operating report, Browns Ferry Nuclear Plant, 1988

    International Nuclear Information System (INIS)

    1989-04-01

    This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant in 1988. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. The vast majority of the exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout. Small amounts of Co-60 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public. 3 refs., 2 figs., 2 tabs

  8. Chemistry in power plants 2011

    International Nuclear Information System (INIS)

    2011-01-01

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

  9. 11. Argentine Congress of Radiological and Nuclear Security

    International Nuclear Information System (INIS)

    2017-01-01

    The 11. Argentine Congress of Radiological and Nuclear Security was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 5 and 6, October 2017. In this event, were presented documents about any of these topics: security systems, licensing of nuclear power plants, criticality accidents, biological radiation effects, NORM, acute radiation syndrome, etc.

  10. Legal provisions governing gaseous effluents radiological monitoring

    International Nuclear Information System (INIS)

    Winkelmann, I.

    1985-01-01

    This contribution explains the main provisions governing radiological monitoring of gaseous effluents from LWR type nuclear power plants. KTA rule 1503.1 defines the measuring methods and tasks to be fulfilled by reactor operators in order to safeguard due monitoring and accounting of radioactive substances in the plants' gaseous effluents. The routine measurements are checked by a supervisory programme by an independent expert. The routine controls include analysis of filter samples, comparative measurement of radioactive noble gases, interlaboratory comparisons, and comparative evaluation of measured values. (DG) [de

  11. Planning for spontaneous evacuation during a radiological emergency

    International Nuclear Information System (INIS)

    Johnson, J.H. Jr.

    1984-01-01

    The Federal Emergency Management Agency's (FEMA's) radiological emergency preparedness program ignores the potential problem of spontaneous evacuation during a nuclear reactor accident. To show the importance of incorporating the emergency spatial behaviors of the population at risk in radiological emergency preparedness and response plans, this article presents empirical evidence that demonstrates the potential magnitude and geographic extent of spontaneous evacuation in the event of an accident at the Long Island Lighting Company's Shoreham Nuclear Power Station. The results indicate that, on the average, 39% of the population of Long Island is likely to evacuate spontaneously and thus to cast an evacuation shadow extending at least 25 miles beyond the plant. On the basis of these findings, necessary revisions to FEMA's radiological emergency preparedness program are outlined

  12. Thermal power plant design and operation

    CERN Document Server

    Sarkar, Dipak

    2015-01-01

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

  13. A methodology for nuclear power plant operational events evaluation

    International Nuclear Information System (INIS)

    Araujo, Jeferson

    2015-01-01

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

  14. A methodology for nuclear power plant operational events evaluation

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  15. Determination of the sources of the airborne physico-chemical 131I species in a PWR power plant

    International Nuclear Information System (INIS)

    Deuber, H.; Wilhelm, J.G.

    1978-01-01

    In a 1300 MWE PWR power plant the sources of the airborne 131 I species were determined over a period of 5 months. During power operation the main source of the radiologically decisive elemental 131 I was the exhaust from the hoods in which samples from the primary coolant are taken and processed. During refueling outage elemental 131 I was mainly contributed by the containment purge air. By efficient filtration of these exhausts, a reduction of the ingestion dose, caused by the total 131 I stack release, by a factor of nearly 4 during power operation and of possibly 10 during refueling outage can be accomplished. (author)

  16. Small-scale power plant potential in Finland

    International Nuclear Information System (INIS)

    Helynen, S.

    1993-01-01

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

  17. Thermal Power Plant Performance Analysis

    CERN Document Server

    2012-01-01

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

  18. Comparative study of radiological assessment impact of nuclear power plant and coal-fired power plant: the atmospheric dispersion factor (χ/Q) in Muria Peninsula, Jepara

    International Nuclear Information System (INIS)

    Umbara, H.; Syahrir; Yatim, S.

    1997-01-01

    The atmospheric dispersion factor (χ/Q) in Muria Peninsula, Jepara was carried out to calculate the exposure dose to public from nuclear power plant and coal-fired plant. The dispersion factor (χ/Q) value was calculated with mathematical model and diffusion equation. Parameter used as the input data was taken from meteorological data of Ujung Watu site within one year (August 1994 - July 1995) to obtain joint frequency distribution data which were the percentage of wind speed and stability class for 16 sector within one year. The results indicated that the highest dispersion factor (χ/Q) within 300 - 700 m radius from point of release is 4.750E-07 - 8.238E-07 second/m 3 for north west direction (author)

  19. Power control of the Angra-2 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1986-01-01

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

  20. Organizing nuclear power plant operation

    International Nuclear Information System (INIS)

    Adams, H.W.; Rekittke, K.

    1987-01-01

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

  1. Advanced power plant materials, design and technology

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  2. Radiological emergency response - a functional approach

    International Nuclear Information System (INIS)

    Chowdhury, Prosanta

    1997-01-01

    The radiological emergency response program in the State of Louisiana is discussed. The improved approach intends to maximize the efficiency for both nuclear power plant and radiological emergency response as a whole. Several broad-based components are identified: cluster of 'nodes' are generated for each component; these 'nodes' may be divided into 'sub-nodes' which will contain some 'attributes'; 'relational bonds' among the 'attributes' will exist. When executed, the process begins and continues with the 'nodes' assuming a functional and dynamic role based on the nature and characteristics of the 'attributes'. The typical response based on stand-alone elements is eliminated; overlapping of functions is avoided, and is produced a well-structure and efficient organization

  3. 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.)

  4. Cooling towers of nuclear power plants

    International Nuclear Information System (INIS)

    Mikyska, L.

    1986-01-01

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

  5. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

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

  6. Nuclear power plants and the environment

    Energy Technology Data Exchange (ETDEWEB)

    Barabas, K [Ceskoslovenska Komise pro Atomovou Energii, Prague

    1978-05-01

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

  7. Nuclear power plants and the environment

    International Nuclear Information System (INIS)

    Barabas, K.

    1978-01-01

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

  8. 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)

  9. Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger

    International Nuclear Information System (INIS)

    Olivieri, Luis E.; Zanni, Pablo A.

    2000-01-01

    Atucha I nuclear power plant moderator system operates with highly radioactive heavy water, a pressure of 115 Bar and temperatures of about 200 C degrees. In March 2000, an increasing leakage of heavy water to the conventional thermal circuit was detected, conducting the plant to a shut down. The development of a number of actions and measures were taken, in order to plug this leakage. The leakage was found in a heat exchanger, which is located in a place of difficult access, with a high radiological yield and which, according to design, it was not considered to be mechanically repaired. It is a U bend tubes heat exchanger, weighting about 20 tons, and with a heavy water flow of 800 tons/h on the primary circuit, and 950 tons/h of ordinary water on the secondary side. Foreseeing this event, it had been designed and constructed special equipment and procedures, by means of a contract, with the Company INVAP SA. Repair works were carried out within a period of eighty-six (86) days, from which, forty five days were used to repair the component itself. A considerable amount of time was used to prepare simulators and the training of personnel. Due to the high radiological yield and the strict care of radiological standards, it was necessary the participation of 300 persons, integrating a collective dose of 4,86 Sv-m. It was necessary the construction of platforms and auxiliary stairs so as to make the work place accessible, as well as lifting and movement devices for heavy components, since this area does not have such kind of facilities. Welding and cutting machines remote controlled as well as manipulators which operated in front of the exchanger tube sheet were used. The aim was the reduction of dose values as much as possible. Special shielding were developed and in some cases it was necessary the adoption of drastic measures such as the cutting of bolts or pipes. The failure was detected and the tube was plugged. Also were plugged those tubes with wall thickness

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

    International Nuclear Information System (INIS)

    Jiao Feng; Hou Qinmai; Che Shuwei

    2013-01-01

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

  11. 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

  12. Report on countermeasure to plant life management of the nuclear power plants at three electric power companies

    International Nuclear Information System (INIS)

    1999-01-01

    Three nuclear power reactors of the Fukushima-1 nuclear power plant, the Mihama-1 power plant and the Tsuruga-1 power plant were investigated according to the estimation plan shown in the Fundamental Concept on Plant Life Management of Agency of Natural Resources and Energy, Ministry of International Trade and Industry on April, 1996. Their reports contained the technical evaluation against, the responsive items to and the future examinations of the plant life management. In special, in the responsive items, some items to be added to the present maintenance process and some technical developmental problems are described in details and concretely. (G.K.)

  13. Radiological impact of the storage of solid wastes from coal-fored power plants

    International Nuclear Information System (INIS)

    Hugon, J.; Caries, J.C.; Patellis, A.; Roussel, S.

    1983-01-01

    Solid wastes from the coal-fired power plant of GARDANNE are stared in piles, outside near the unit. The coal contains a high proportion of sulfur, so the storage pile is a very reducing middle. The radium coming from the ore, which is mostly retained in the bottom ashes, could then be solubilized again, by physicochemical processes, leached by the rain and reach the nearest population through the food-chain pathways. Leaching-tests where made with three sampling series. The measurement datas show that only 15% of the 226 Ra can be solved and that the Ra 226 observed concentrations in vegetal samples come mostly from transportation of dust by the wind [fr

  14. 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.)

  15. Automation technology in power plants

    International Nuclear Information System (INIS)

    Essen, E.R.

    1995-01-01

    In this article a summery of the current architecture of modern process control systems in power plants and future trends have been explained. The further development of process control systems for power plants is influenced both by the developments in component and software technologies as well as the increased requirements of the power plants. The convenient and low cost configuration facilities of new process control systems have now reached a significance which makes it easy for customers to decide to purchase. (A.B.)

  16. Methodology for environmental radiological assessment applied to the decommissioning of the Italian Nuclear Power Plants

    International Nuclear Information System (INIS)

    Petraglia, A.; Sabbarese, C.; Terrasi, F.; D'Onofrio, A.; Visciano, L.; Alfieri, S.; Esposito, A.M.; Migliore, G.; Mancini, F.; Napier, B.

    2006-01-01

    The present study is the second part of a program of characterization of the sites surrounding the Italian Nuclear Power Plants (NPPs) which are currently involved in decommissioning activities. In the first phase of the project an analysis of the Garigliano NPP was carried out and the reference groups of the population were established on the basis of a socio-economical survey of the site. A field campaign was carried out aiming to assess the 'zero level' due to the natural and past anthropogenic radioactivity [1, 2]. In the second part the study was extended to the other three Italian NPPs, namely Latina, Trino and Caorso. The radiological doses due to the planned and accidental releases during the decommissioning phases were calculated on the basis of environmental parameters related to the area of interest. These parameters include climatological, hydrological, geo morphological data. The implementation of transport and diffusion specific models of radionuclides in the environment was another step for the dose calculation using specific evaluation software. The current software (V.A.D.O.S.C.A.) specially built and used in the past for Italian NPPs has been replaced by the framework F.R.A.M.E.S.-GenII 2.0 which is a calculation code updated in the transport model and in the reference laws, and running under new computer operating systems. This code has been used to design the possible scenarios for each site by using conceptual calculation models which contain local input data and adequate dispersion models. The input data consist of (a) way and amount of radionuclide release in planned and accidental cases, (b) reference groups of population and their food habits, (c) climatic data of the area understudy. The dispersion models are implemented by considering releases in water (canal, river, sea) and in atmosphere. In order to allow a simplified, efficient and friendly utilisation of the Frames-GenII code, it has been enriched with a routine, D.S.A.-Reader, which

  17. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing plants in the European Community. Discharge data 1972-1976 radiological aspects

    International Nuclear Information System (INIS)

    Luykx, F.; Fraser, G.

    1978-04-01

    The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

  18. Radiological Environmental Protection for LCLS-II High Power Operation

    Directory of Open Access Journals (Sweden)

    Liu James

    2017-01-01

    Full Text Available The LCLS-II superconducting electron accelerator at SLAC plans to operate at up to 4 GeV and 240 kW average power, which would create higher radiological impacts particularly near the beam loss points such as beam dumps and halo collimators. The main hazards to the public and environment include direct or skyshine radiation, effluent of radioactive air such as 13N, 15O and 41Ar, and activation of groundwater creating tritium. These hazards were evaluated using analytic methods and FLUKA Monte Carlo code. The controls (mainly extensive bulk shielding and local shielding around high loss points and monitoring (neutron/photon detectors with detection capabilities below natural background at site boundary, site-wide radioactive air monitors, and groundwater wells were designed to meet the U.S. DOE and EPA, as well as SLAC requirements. The radiological design and controls for the LCW systems [including concrete housing shielding for 15O and 11C circulating in LCW, 7Be and erosion/corrosion products (22Na, 54Mn, 60Co, 65Zn, etc. captured in resin and filters, leak detection and containment of LCW with 3H and its waste water discharge; explosion from H2 build-up in surge tank and release of radionuclides] associated with the high power beam dumps are also presented.

  19. Conceptual basic and status of nuclear power plant decommissioning effort in the Russian Federation

    International Nuclear Information System (INIS)

    Glazounov, V.; Khamyanov, L.

    1998-01-01

    Decommissioning of nuclear power plants, although a usual phase in nuclear facility life cycle still has significant peculiarities due to radioactive contamination of NPP equipment and structural elements. This paper deals with the phases in decommissioning process, as follows: NPP shutdown, meaning end of commercial operation; NPP unit mothballing, radiation review of the unit to justify particular concept of decommissioning; extended hold-up, which means maintaining of contaminated equipment in the isolated zone under radiologically safe conditions; unit dismantling and burial. Status of NPP decommissioning effort in Russia is described

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

    International Nuclear Information System (INIS)

    Lenasson, Magnus

    2015-01-01

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

  1. Angra nuclear plant - environmental control program

    International Nuclear Information System (INIS)

    Kircher, E.; Cruz, E.S. da

    1989-01-01

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

  2. Power control strategy of a photovoltaic power plant for microgrid applications

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  3. Monitored Natural Attenuation as a Remediation Strategy for Nuclear Power Plant Applications

    Science.gov (United States)

    Kim, K.; Bushart, S.

    2009-12-01

    plant sites. One of these remediation technologies is monitored natural attenuation (MNA), which has been widely used in other industries for the remediation of contaminants in soil and groundwater. Monitored natural attenuation (MNA) is a non-intervention, but not a no-action, groundwater and soil remediation approach that involves monitoring the dilution, dispersion, and decay of contaminants to meet remediation objectives. MNA has been commonly applied at sites where soil and groundwater have been contaminated by volatile organic compounds. This method has also been applied to remediation of radiological contamination at U.S. DOE facilities and decommissioning nuclear power plant sites. The EPRI published report (1016764) provides guidance for implementing MNA at nuclear power plants for remediation of radiological contaminants in groundwater and soil. The goal of the EPRI Groundwater Protection program is to bring together experience and technologies - both from within the nuclear industry and other industries - to support the industry’s commitment to environmental stewardship. Results from the program are being published in an extensive series of reports and software, and are being communicated to members in an annual EPRI Groundwater Protection technical exchange workshop.

  4. A nuclear power plant status monitor

    International Nuclear Information System (INIS)

    Chu, B.B.; Conradi, L.L.; Weinzimmer, F.

    1986-01-01

    Power plant operation requires decisions that can affect both the availability of the plant and its compliance with operating guidelines. Taking equipment out of service may affect the ability of the plant to produce power at a certain power level and may also affect the status of the plant with regard to technical specifications. Keeping the plant at a high as possible production level and remaining in compliance with the limiting conditions for operation (LCOs) can dictate a variety of plant operation and maintenance actions and responses. Required actions and responses depend on the actual operational status of a nuclear plant and its attendant systems, trains, and components which is a dynamic situation. This paper discusses an Electric Power Research Institute (EPRI) Research Project, RP 2508, the objective of which is to combine the key features of plant information management systems with systems reliability analysis techniques in order to assist nuclear power plant personnel to perform their functions more efficiently and effectively. An overview of the EPRI Research Project is provided along with a detailed discussion of the design and operation of the PSM portion of the project

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

    International Nuclear Information System (INIS)

    1984-01-01

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

  6. Determination of radiation doses caused by release into the atmosphere by nuclear power plants, based on measurement of emission and immission

    International Nuclear Information System (INIS)

    Ekler, B.; Deme, S.

    2006-01-01

    The radiation impact of nuclear facilities, and the nuclear power plants as well, can be determined by using two methods. The first one calculates the dose of critical group of population based on the release, meteorological and hydrological parameters. The second method gives an estimate of the additional dose caused by the nuclear facility from the radiological measurements in the environment. This article compares this two methods for the release in the atmosphere, and gives an estimate of the relative error. The comparison can be applied for cases when the atmospheric pollution is released from a point type source, so for the conventional power plants as well. (author)

  7. Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  8. Summary of nuclear power plant construction

    International Nuclear Information System (INIS)

    Tamura, Saburo

    1973-01-01

    Various conditions for the construction of nuclear power plants in Japan without natural resources were investigated. Expansion of the sites of plants, change of reactor vessels, standardization of nuclear power plants, possiblity of the reduction of construction period, approaching of nuclear power plants to consuming cities, and group construction were studied. Evaluation points were safety and economy. Previous sites of nuclear power plants were mostly on plane ground or cut and enlarge sites. Proposals for underground or offshore plants have been made. The underground plants were made at several places in Europe, and the ocean plant is now approved in U.S.A. as a plant on a man-made island. Vessels for containing nuclear reactors are the last barriers to the leakage of radioactive substance. At the initial period, the vessels were made of steel, which were surrounded by shielding material. Those were dry well type containers. Then, vessel type changed to pressure-suppression type wet containers. Now, it tends to concrete (PC or RC) type containers. There is the policy on the standardization of nuclear power plants by U.S.A.E.C. in recent remarkable activity. The merit and effect of the standardization were studied, and are presented in this paper. Cost of the construction of nuclear power plants is expensive, and interest of money is large. Then, the reduction of construction period is an important problem. The situations of plants approaching to consuming cities in various countries were studied. Idea of group construction is described. (Kato, T.)

  9. Implications of power uprates on safety margins of nuclear power plants. Report of a technical meeting

    International Nuclear Information System (INIS)

    2004-09-01

    The safety of nuclear power plants (NPPs) is based on the defence in depth concept, which relies on successive physical barriers (fuel matrix, cladding, primary system pressure boundary and containment) and other provisions to control radioactive materials and on multiple levels of protection against damage to these barriers. Deterministic safety analysis is an important tool for conforming the adequacy and efficiency of provisions within the defence in depth concept and is used to predict the response of an NPP in predetermined operational states. This type of safety analysis applies a specific set of rules and specific acceptance criteria. Deterministic analysis is typically focused on neutronic, thermohydraulic, radiological and structural aspects, which are often analysed with different computational tools. The advanced computational tools developed for deterministic safety analysis are used for better establishment and utilization of licensing margins or safety margins in consideration of analysis results. At the same time, the existence of such margins ensures that NPPs operate safely in all modes of operation and at all times. To properly assess and address the existing margins and to be able to take advantage of unnecessary conservatisms, state of the art analytical tools intended for safety assessment have been developed. Progress made in the development and application of modern codes for safety analysis and better understanding of phenomena involved in plant design and operation enable the analysts to determine safety margins in consideration of analysis results (licensing margins) with higher precision. There is a general tendency for utilities to take advantage of unnecessarily large conservatisms in safety analyses and to utilize them for reactor power uprates, better utilization of nuclear fuel, higher operational flexibility and for justification of lifetime extension. The present publication sets forth the results of a Technical Meeting on the

  10. 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

  11. 75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2010-10-29

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

  12. Toward raising the higher level of radiological nursing

    International Nuclear Information System (INIS)

    Kusama, Tomoko; Ban, Nobuhiko; Ono, Koji

    2013-01-01

    The role and purpose of nursing in the radiological field are discussed with essentials of radiological nursing for raising its higher level and needed fundamental education. The discussion is from the thought that, at Fukushima Nuclear Power Plant Accident (Mar. 2011), general medical staff including nurses are rather insufficient of radiological knowledge like the exposure, radiation effect and risk. In the medical radiological field, nurses are expected to play roles of arranging the circumstance for patient's ease like explanation about health effect/risk, appropriate nursing of them after radiological diagnosis, radiation protection of nurses themselves, and of environment. At such an emergency as the Accident, care for the acutely exposed victims, their decontamination and responding to patient's concern are necessary. At the later phase, also needed are nursing of victims undergoing health management done by authorities and of radiological workers concerned as well as the third item above. Therefore, fundamentals of radiological knowledge such as physics, exposure, health effects, protection, contamination, legal rules and risk communication are required in the education of nurses. Otherwise, this education can be conducted as a part of safety security and physical assessment. The Accident also gives us the importance of radiological risk communication with its victims. (T.T.)

  13. The performance trends of nuclear power plants worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Glorian, D. [Electricite de France (EDF), 93 - Saint-Denis (France)

    2001-07-01

    Looking back to the worldwide operating experience feedback, which performance trends and conclusions could be drawn up? What is the specific situation of the French nuclear units, in comparison with the average worldwide performance? The performance of a unit or group of facilities is measured not only in technical terms (safety, availability, load control capability), but also from an economic and financial standpoint (operating and maintenance costs, fuel costs, etc). Performance in terms of radiological protection and on-the-job safety, as well as environmental protection, is also monitored in order to give the broadest possible overview of nuclear power plant performance. The main technical results are presented on the basis of selected performance indicators. The results obtained by French units are benchmarked against those of other PWR facilities in operation around the world, in accordance with comparisons made by the World Association of Nuclear Operators (WANO). (author)

  14. The performance trends of nuclear power plants worldwide

    International Nuclear Information System (INIS)

    Glorian, D.

    2001-01-01

    Looking back to the worldwide operating experience feedback, which performance trends and conclusions could be drawn up? What is the specific situation of the French nuclear units, in comparison with the average worldwide performance? The performance of a unit or group of facilities is measured not only in technical terms (safety, availability, load control capability), but also from an economic and financial standpoint (operating and maintenance costs, fuel costs, etc). Performance in terms of radiological protection and on-the-job safety, as well as environmental protection, is also monitored in order to give the broadest possible overview of nuclear power plant performance. The main technical results are presented on the basis of selected performance indicators. The results obtained by French units are benchmarked against those of other PWR facilities in operation around the world, in accordance with comparisons made by the World Association of Nuclear Operators (WANO). (author)

  15. VGB Congress 'Power Plants 2006'

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    The VGB Congress 'Power Plants' took place in Dresden, 27 th to 29 th September 2006 under the auspices of the Federal Minister for Economics and Technology, Michael Glos. The motto of this year's Congress was 'Future becomes Reality - Investments in New Power Plants'. More than 1,200 participants from Germany and abroad attended the plenary and technical lectures on the topics 'Market and Competition' as well as 'Technology, Operation and Environment' for information and discussion. Special papers were dealing with further issues like 'Generation Market in Europe', 'Clean Power Technology Platform', French policy for new power plants as well as potentials and technology of renewables. (orig.)

  16. 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

  17. Virtual power plant mid-term dispatch optimization

    International Nuclear Information System (INIS)

    Pandžić, Hrvoje; Kuzle, Igor; Capuder, Tomislav

    2013-01-01

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

  18. Facilities and medical care for on-site nuclear power plant radiological emergencies

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The operation of a nuclear power plant introduces risks of injury or accidents that could also result in the exposure of personnel to radiation or radioactive materials. It is important in such an event to have adequate first aid and medical facilities, supplies, equipment, transportation capabilities and trained personnel available to provide necessary care. This standard provides guidance for first aid during an emergency and for initial medical care of those overexposed to penetrating radiation or contaminated with radioactive material or radionuclides. Recommendations cover facilities, supplies, equipment and the extent of care on-site, where first aid and initial care may be provided, and off-site at a local hospital, where further medical and surgical care may be provided. Additional recommendations are also provided for the transportation of patients and the training of personnel. A brief discussion of specialized care is provided in an appendix

  19. Nuclear power plants maintenance

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

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

  20. Nuclear power plant outages

    International Nuclear Information System (INIS)

    1998-01-01

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

  1. Developing a virtual reality application for training Nuclear Power Plant operators: Setting up a database containing dose rates in the refuelling plant

    International Nuclear Information System (INIS)

    Rodenas, J.; Zarza, I.; Burgos, M. C.; Felipe, A.; Sanchez-Mayoral, M. L.

    2004-01-01

    Operators in Nuclear Power Plants can receive high doses during refuelling operations. A training programme for simulating refuelling operations will be useful in reducing the doses received by workers as well as minimising operation time. With this goal in mind, a virtual reality application is developed within the framework of the CIPRES project. The application requires doses, both instantaneous and accumulated, to be displayed at all times during operator training. Therefore, it is necessary to set up a database containing dose rates at every point in the refuelling plant. This database is based on radiological protection surveillance data measured in the plant during refuelling operations. Some interpolation routines have been used to estimate doses through the refuelling plant. Different assumptions have been adopted in order to perform the interpolation and obtain consistent data. In this paper, the procedures developed to set up the dose database for the virtual reality application are presented and analysed. (authors)

  2. Physical and financial virtual power plants

    International Nuclear Information System (INIS)

    Willems, Bert

    2005-01-01

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

  3. Development of a dose database in the refuelling scenario of a nuclear power plant for a virtual reality application

    International Nuclear Information System (INIS)

    Rodenas, J.; Zarza, I.; Pascual, A.; Felipe, A.; Sanchez-Mayoral, M.L.

    2002-01-01

    Operators in Nuclear Power Plants can receive high doses during refuelling operation. A training program simulating refuelling operations will be useful to reduce doses received by workers as well as to minimise operation time. With this goal in mind a Virtual Reality application is developed in the frame of CIPRES Project (Calculos Interactivos de Proteccion Radiologica en un Entorno de Simulacion - Interactive Calculations of Radiological Protection in a Simulation Environment), a RD project sponsored by IBERINCO and developed jointly by IBERINCO and the Nuclear Engineering Department of the Polytechnic University of Valencia. The Virtual Reality application requires the possibility of displaying doses, both instantaneous and accumulated, at all times during the operator training. Therefore, it is necessary to elaborate a database containing dose rates at every point of the refuelling plant. This database is elaborated from Radiological Protection Surveillance data measured throughout the plant during refuelling operation. To estimate doses throughout the refuelling plant some interpolation routines have been used. Different assumptions have been adopted in order to perform the interpolation and obtain consistent data. In this paper, procedures developed to elaborate the dose database for the Virtual Reality application are presented and analysed

  4. 75 FR 77919 - Carolina Power & Light Company Shearon Harris Nuclear Power Plant, Unit 1; Environmental...

    Science.gov (United States)

    2010-12-14

    ... affect radiation exposures to plant workers and members of the public. Therefore, no changes or different... socioeconomic resources. Therefore, no changes to or different types of non-radiological environmental impacts...

  5. Training of power plant operating personnel

    International Nuclear Information System (INIS)

    Kraftwerksschule, E.V.

    1986-01-01

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

  6. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Pack, R.W.

    1978-01-01

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

  7. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    Machiba, Hiroshi; Sasaki, Norio

    1990-01-01

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

  8. Regulatory Practices on Ageing Management and Long Term Operation of Nuclear Power Plants in the Ibero-American Region. Results of the FORO/IAEA Programme on Nuclear and Radiation Safety in Ibero-America

    International Nuclear Information System (INIS)

    2014-09-01

    Although the operating lifetime of a nuclear power plant was originally anticipated to be in the range of 30-40 years, 200 of the 434 currently in operation are over 30 years old. In this context, Member States have assigned high priority to continuing the operation of nuclear power plants beyond the lifetime initially planned - while also maintaining the highest safety conditions possible. It is thus essential to encourage international cooperative efforts in the development of safety regulatory practices on ageing management and long term operation. Established in 1997, the Ibero-American Forum of Radiological and Nuclear Regulatory Agencies (FORO) aims to strengthen its members' radiological and nuclear safety regulatory organizations. Through a regional network of radiological and nuclear safety regulators, States in the Ibero-American region have worked together to strengthen radiation protection for patients, to improve safety at radiation installations, to tightten controls on radioactive sources used in medicine, agriculture and industry, and to improve safety and security at nuclear power plants. Since FORO's creation, it has cooperated with the IAEA in areas of mututal interest, and a technical programme administered by the IAEA was established in 2003 and formalized in Practical Arrangements signed in 2010. This publication presents the results of the 2009-2010 FORO/IAEA project on regulatory practices on ageing management and safety considerations for extending the operating lifetime of nuclear power plants. The purpose of the project was to provide nuclear regulators in the region with guidance on regulatory criteria, assessment, regulatory inspection and periodic safety reviews relating to ageing management and long term operation of nuclear power plants. The results are presented in a set of four reports, with guidelines for FORO members and a summary report of the project. These reports contain valuable information for the development of future

  9. Radiological emergency response - a functional approach

    Energy Technology Data Exchange (ETDEWEB)

    Chowdhury, Prosanta [Louisiana Radiation Protection Div., Baton Rouge, LA (United States)

    1997-12-31

    The radiological emergency response program in the State of Louisiana is discussed. The improved approach intends to maximize the efficiency for both nuclear power plant and radiological emergency response as a whole. Several broad-based components are identified: cluster of `nodes` are generated for each component; these `nodes` may be divided into `sub-nodes` which will contain some `attributes`; `relational bonds` among the `attributes` will exist. When executed, the process begins and continues with the `nodes` assuming a functional and dynamic role based on the nature and characteristics of the `attributes`. The typical response based on stand-alone elements is eliminated; overlapping of functions is avoided, and is produced a well-structure and efficient organization 1 ref., 6 figs.; e-mail: prosanta at deq.state.la.us

  10. 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.

  11. TAPCHAN Wave Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    1983-10-01

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

  12. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

    1998-10-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  13. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

    1998-01-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  14. Plant life management and maintenance technologies for nuclear power plants

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  15. Wind power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kling, A

    1977-01-13

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

  16. Radiological characterization of waste products at a Catalan drinking water treatment plant - Radiological characterization of waste products of one Catalan drinking water treatment plant

    Energy Technology Data Exchange (ETDEWEB)

    Camacho, A.; Montana, M.; Serrano, I.; Blazquez, S.; Duch, M.A. [Institut de Tecniques Energetiques. Universitat Politecnica de Catalunya, ETSEIB. Diagonal 647. 08028 Barcelona (Spain); Montes, S.; Ganzer, M.; Devesa, R. [Aigues de Barcelona, AGBAR. Laboratory, General Batet, 5-7, 08028 Barcelona (Spain)

    2014-07-01

    Conventional Drinking Water Treatment Plants (DWTP) have a fairly standard sequence of processes which essentially consist in solids separation using physical processes such as settling and filtration, and chemical processes such as coagulation and disinfection. Consequently large quantities of solid wastes or sludge are generated every year by DWTP. These solid wastes may contain all kind of pollutants, including significant levels of radioactivity and may cause a radiological impact on the operating personnel, but also on the public if the waste is recycled, e.g. the use of sludge as fertilizer or cement manufacturing. In this work it has been studied the radioactivity content of waste products of one DWTP. The selected DWTP treats water mainly taken from the Llobregat River and also ground water. The treatment plant has a maximum treatment capacity of 5.5 m{sup 3}/s, and provides almost 50% of the annual drinking water in Barcelona metropolitan area (population equivalent of the plant: 4,856,579). This plant has been selected taking into account both variations in water source and the treatment applied. During the period July 2007 - March 2009 a temporal study of radio-nuclides present in sludge produced by the decanter cleaning process was conducted. The temporal study was made taking into account the particular weather conditions in Spain, at least one sampling campaign per season. In these samples naturally gamma emitters from the {sup 238}U and {sup 232}Th series were detected with activities similar to the arithmetic mean found in Spanish soils so no increase in natural radiation are produced by the uses of these sludge. Furthermore, no seasonal tendency could be observed in the studied period for both series within the uncertainties associated with the results. Radiological hazard effects were also evaluated by the external hazard index because one of the end-uses of this sludge is the cement manufacturing. In 2009 the treatment plant was modified and

  17. Reliability of emergency ac power systems at nuclear power plants

    International Nuclear Information System (INIS)

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

    1983-07-01

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

  18. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

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

  19. 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.)

  20. 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

  1. 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

  2. Clearance of very low level radioactive waste in spanish nuclear power plants

    International Nuclear Information System (INIS)

    Alvarez Mir, F.

    2001-01-01

    According to present Spanish legislation a radioactive waste is defined as any material or waste product, without any possible planned use, that contains or is contaminated with radionuclides in concentrations or activity levels higher than those established by the Regulatory Authorities. Legally, this situation allows to develop a conventional management of very low level radioactive waste, by checking the negligibility of their radiological impact, and thus obtaining the corresponding Authorization to treat them as conventional waste. This presentation describes the clearance project of contaminated oils from spanish nuclear power plants. The on-site management includes: -) preliminary settling, centrifugation and filtration; -) oil purification; and -) radiological characterization. The off-site management includes the following operations: -) transportation to the facility where treatment is developed (dilution); -) temporary storage (decay); -) transportation to the place where final management is carried out; -) oil burning (dilution); and management of ashes and other combustion products. An annual amount of 70 m 3 /year (63 MBq) of very low contaminated oil with a specific concentration of 1 Bq/g could be disposed off. (A.C.)

  3. The operation of nuclear power plants

    International Nuclear Information System (INIS)

    Brosche, D.

    1992-01-01

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

  4. Direct FuelCell/Turbine Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hossein Ghezel-Ayagh

    2008-09-30

    This report summarizes the progress made in development of Direct FuelCell/Turbine (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T system employs an indirectly heated Turbine Generator to supplement fuel cell generated power. The concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, minimal emissions, reduced carbon dioxide release to the environment, simplicity in design, direct reforming internal to the fuel cell, and potential cost competitiveness with existing combined cycle power plants. Proof-of-concept tests using a sub-MW-class DFC/T power plant at FuelCell Energy's (FCE) Danbury facility were conducted to validate the feasibility of the concept and to measure its potential for electric power production. A 400 kW-class power plant test facility was designed and retrofitted to conduct the tests. The initial series of tests involved integration of a full-size (250 kW) Direct FuelCell stack with a 30 kW Capstone microturbine. The operational aspects of the hybrid system in relation to the integration of the microturbine with the fuel cell, process flow and thermal balances, and control strategies for power cycling of the system, were investigated. A subsequent series of tests included operation of the sub-MW Direct FuelCell/Turbine power plant with a Capstone C60 microturbine. The C60 microturbine extended the range of operation of the hybrid power plant to higher current densities (higher power) than achieved in initial tests using the 30kW microturbine. The proof-of-concept test results confirmed the stability and controllability of operating a fullsize (250 kW) fuel cell stack in combination with a microturbine. Thermal management of the system was confirmed and power plant operation, using the microturbine as the only source of fresh air supply

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-12-31

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

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  8. Damping of Low Frequency Power System Oscillations with Wind Power Plants

    DEFF Research Database (Denmark)

    Adamczyk, Andrzej Grzegorz

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

  9. Thermodynamic optimization of power plants

    NARCIS (Netherlands)

    Haseli, Y.

    2011-01-01

    Thermodynamic Optimization of Power Plants aims to establish and illustrate comparative multi-criteria optimization of various models and configurations of power plants. It intends to show what optimization objectives one may define on the basis of the thermodynamic laws, and how they can be applied

  10. Accident analysis for nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    Deterministic safety analysis (frequently referred to as accident analysis) is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). Owing to the close interrelation between accident analysis and safety, an analysis that lacks consistency, is incomplete or is of poor quality is considered a safety issue for a given NPP. Developing IAEA guidance documents for accident analysis is thus an important step towards resolving this issue. Requirements and guidelines pertaining to the scope and content of accident analysis have, in the past, been partially described in various IAEA documents. Several guidelines relevant to WWER and RBMK type reactors have been developed within the IAEA Extrabudgetary Programme on the Safety of WWER and RBMK NPPs. To a certain extent, accident analysis is also covered in several documents of the revised NUSS series, for example, in the Safety Requirements on Safety of Nuclear Power Plants: Design (NS-R-1) and in the Safety Guide on Safety Assessment and Verification for Nuclear Power Plants (NS-G-1.2). Consistent with these documents, the IAEA has developed the present Safety Report on Accident Analysis for Nuclear Power Plants. Many experts have contributed to the development of this Safety Report. Besides several consultants meetings, comments were collected from more than fifty selected organizations. The report was also reviewed at the IAEA Technical Committee Meeting on Accident Analysis held in Vienna from 30 August to 3 September 1999. The present IAEA Safety Report is aimed at providing practical guidance for performing accident analyses. The guidance is based on present good practice worldwide. The report covers all the steps required to perform accident analyses, i.e. selection of initiating events and acceptance criteria, selection of computer codes and modelling assumptions, preparation of input data and presentation of the

  11. Possible uses and applications of drones in a nuclear power plant; Posibles usos y aplicaciones de los drones en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Celis del A, L.; Palacios, J.; Rivero, T.; Valero, D., E-mail: lina.celis@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The versatility of drones is one of the strengths that have led to the rapid development of this technology, as they adapt relatively easily to new applications, presenting considerable advantages such as greater energy efficiency, longer life and a significant lower operation cost than manned systems. The current applications of the drones, in addition to the military, are very wide and varied. The nuclear industry represents an important area of opportunity for drones, mainly in response to radiological emergencies, since in this case there is a latent risk of the general population being exposed to high radiation doses. Drones can be used in environments with high chemical and radiological toxicity without endangering human lives. Some of the possible applications of the drones in a nuclear power plant are: perimeter surveillance in physical security, where equipped with a high definition camera can be used as support to physical security systems in general; visual inspection at sites, structures, equipment and pipelines, etc., as part of preventive maintenance in order to avoid the loss of material due to corrosion, oxidation, cracking, subsidence; the visual inspection through thermo-graphic images to be able to detect hot spots in some critical element; measurement and radiological mapping on surfaces to maintain monitoring of radiological safety at nuclear power plant facilities; the monitoring of environmental parameters and the Environmental Impact Assessment to obtain important information to determine the environmental impact of a given area; and accident support by providing information that allows staff to size the magnitude of the damage. (Author)

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

    International Nuclear Information System (INIS)

    Kalincik, L.

    1975-01-01

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

  13. Reliability of the emergency AC power system at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

    1983-01-01

    The reliability of the emergency ac power systems typical of most nuclear power plants was estimated, and the cost and increase in reliability for several improvements were estimated. Fault trees were constructed based on a detailed design review of the emergency ac power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. No one or two improvements can be made at all plants to significantly increase the industry-average emergency ac power system reliability; rather the most beneficial improvements are varied and plant specific. Improvements in reliability and the associated costs are estimated using plant specific designs and failure probabilities

  14. Romanian achievement in hydro-power plants

    International Nuclear Information System (INIS)

    Cardu, M.; Bara, T.

    1998-01-01

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

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

    DEFF Research Database (Denmark)

    Zeni, Lorenzo; Eriksson, Robert; Goumalatsos, Spyridon

    2016-01-01

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

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

    International Nuclear Information System (INIS)

    1999-01-01

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

  17. RASCAL 4.l: evaluation system for the analysis of the radiological consequences

    International Nuclear Information System (INIS)

    Miguel, I. de; Gomez-Arguello, B.

    2012-01-01

    Recently the Spanish Nuclear Safety Council (CSN) has promoted the replacement of the code used in the Spanish Nuclear Power Plants to estimate potential and actual doses due to atmospheric releases. IRDAM Code (interactive Rapid Dose Assessment Model, 1983) by RASCAL Code version 4.1 (Radiological Assessment System for consequence Analysis). This code was developed by the NRC (Nuclear Regulatory Commission) to evaluate releases from nuclear power plants, spent fuel storage pools and casks, fuel cycle facilities and radioactive material handling facilities. RASCAL was officially requested to the Spanish nuclear power plants in February 1st, 2012, and it can be used for external dose assessment and to evaluate the recommended protective action for the public in a specific situation (sheltering, prophylaxis, evacuation, etc.). (Author)

  18. Radiological protection and the Fukushima Daiichi accident. Responses of the key international organisations

    Energy Technology Data Exchange (ETDEWEB)

    Clement, Christopher

    2017-10-01

    The Fukushima Daiichi nuclear power plant accident in March 2011 shook the radiological protection world. All major organisations in the radiological protection field turned their eyes to Japan. Their actions, driven by their mandates, are reflected in their respective landmark reports on the accident. Reports of the International Commission on Radiological Protection, World Health Organisation, United Nations Scientific Committee on the Effects of Atomic Radiation, and International Atomic Energy Agency are summarised. Collaboration between key international organisations is strong, based in part on informal interactions which need to be backed up with formal relations to ensure solid long-term collaboration.

  19. RI Mapping System for Identification of Radiological Contamination in Environmental Water Supply System

    Energy Technology Data Exchange (ETDEWEB)

    Na, Teresa W.; Ha, Jang Ho; Kim, Han Soo; Lee, Seung Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Na, Teresa W.; Lee, Rena [Ewha Womans Univ., Hospital, Seoul (Korea, Republic of)

    2012-03-15

    The interest of radiation protection has risen due to accidents of the Nuclear Power Plant, nuclear terrorism, and the radiological contamination in the city, In this respect, the development of environmental radiation monitoring for the radiological contaminants has been studied. In this study, the experiment for the radiological contamination in the water supply pipe line system has been simulated and preliminarily tested. The CsI(Tl)-PIN diode detectors were used and the preliminary test of radiation monitoring system was performed as multi detection system. The 2D image reconstruction algorithm was also developed for feasibility of the constructed multi-detection system.

  20. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

  1. The radiological accident of Goiania and the acceptance by the public of new nuclear power plants; El accidente radiologico de Goiania y la aceptacion publica de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Meldonian, N L; Mattos, L A.T. [Grupo de Energia e Ambiente, Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)

    1998-12-01

    Misunderstandings on the peaceful uses and the safety of nuclear energy have been a leading cause of apprehension in Brazilian public opinion. A lack of knowledge of the characteristics and destination of radioactive wastes and negative media coverage of the use of nuclear energy have aggravated this situation. Believing that applications of nuclear energy are harmful to the population`s welfare and the environment, Brazilian public opinion is opposed to the utilization of nuclear energy, and in particular to the construction of new nuclear power plants. For this reason, the Brazilian nuclear sector should promote a more intensive programme of public discussion, directed not solely at the technical and scientific communities, but also at the Brazilian public at large. Such a campaign would contribute towards a better understanding by Brazilian society of the different uses of nuclear energy and would present arguments in support of the benefits of this form of energy. Moreover, a campaign of this kind would show that negative associations about the use of electricity derived from nuclear power, which are based on the Goiania radiological accident, are not justified. (author) 10 refs, 5 tabs

  2. 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.)

  3. 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.)

  4. Possible Power Estimation of Down-Regulated Offshore Wind Power Plants

    DEFF Research Database (Denmark)

    Gögmen, Tuhfe

    The penetration of offshore wind power is continuously increasing in the Northern European grids. To assure safety in the operation of the power system, wind power plants are required to provide ancillary services, including reserve power attained through down-regulating the wind farm from its...... power plant. The developed procedure, the PossPOW algorithm, can also be used in the wind farm control as it yields a real-time wind farm power curve. The modern wind turbines have a possible power signal at the turbine level and the current state of the art is to aggregate those signals to achieve...... the wind farm scale production capacity. However the summation of these individual signals is simply an over-estimation for the wind power plant, due to reduced wake losses during curtailment. The determination of the possible power with the PossPOW algorithm works as follows: firstly the second...

  5. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    1998-01-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

  6. 4. Nuclear power plant component failures

    International Nuclear Information System (INIS)

    1990-01-01

    Nuclear power plant component failures are dealt with in relation to reliability in nuclear power engineering. The topics treated include classification of failures, analysis of their causes and impacts, nuclear power plant failure data acquisition and processing, interdependent failures, and human factor reliability in nuclear power engineering. (P.A.). 8 figs., 7 tabs., 23 refs

  7. Man and nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    According to the Inst. fuer Unfallforschung/TUeV Rheinland, Koeln, the interpretation of empirical data gained from the operation of nuclear power plants at home and abroad during the period 1967-1975 has shown that about 38% of all reactor accidents were caused by human failures. These occured either during the design and construction, the commissioning, the reconditioning or the operation of the plants. This very fact stresses human responsibility for the safety of nuclear power plants, in spite of those plants being automated to a high degree and devices. (orig.) [de

  8. Reactor power control device in BWR power plant

    International Nuclear Information System (INIS)

    Kurosawa, Tsuneo.

    1997-01-01

    The present invention provides a device for controlling reactor power based on a start-up/shut down program in a BWR type reactor, as well as for detecting deviation, if occurs, of the power from the start-up/shut down program, to control a recycling flow rate control system or control rod drive mechanisms. Namely, a power instruction section successively executes the start-up/shut down program and controls the coolant recycling system and the control rod driving mechanisms to control the power. A current state monitoring and calculation section receives a process amount, calculates parameters showing the plant state, compares/monitors them with predetermined values, detecting the deviation, if occurs, of the plant state from the start-up/shut down program, and prevents output of a power increase control signal which leads to power increase. A forecasting and monitoring/calculation section forecasts and calculates the plant state when not yet executed steps of the start-up/shut down program are performed, stops the execution of the start-up/shut down program in the next step in a case of forecasting that the results of the calculation will deviate from the start-up/shut down program. (I.S.)

  9. International power plant business

    Energy Technology Data Exchange (ETDEWEB)

    Grohe, R.

    1986-03-03

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

  10. Ecological impacts and damage - comparison of selected components for nuclear and conventional power plants (example of Mochovce nuclear power plant)

    International Nuclear Information System (INIS)

    Bucek, M.

    1984-01-01

    A comparison is given of ecological damage for the nuclear power plant in Mochovce and a conventional power plant with the same power. Ecological effects and damage are divided into three groups: comparable damage, ecological damage caused only by conventional power plants and ecological damage caused only by nuclear power plants. In the first group the factors compared are land requisition, consumption of utility water and air consumption. In the second group are enumerated losses of crops (cereals, sugar beet, potatoes, oleaginous plants) and losses caused by increased disease rate owing to polluted environment by conventional power plants. In the third group health hazards are assessed linked with ionizing radiation. Also considered are vent stack escapes. (E.S.)

  11. Space nuclear reactor power plants

    International Nuclear Information System (INIS)

    Buden, D.; Ranken, W.A.; Koenig, D.R.

    1980-01-01

    Requirements for electrical and propulsion power for space are expected to increase dramatically in the 1980s. Nuclear power is probably the only source for some deep space missions and a major competitor for many orbital missions, especially those at geosynchronous orbit. Because of the potential requirements, a technology program on space nuclear power plant components has been initiated by the Department of Energy. The missions that are foreseen, the current power plant concept, the technology program plan, and early key results are described

  12. Methodology for Scaling Fusion Power Plant Availability

    International Nuclear Information System (INIS)

    Waganer, Lester M.

    2011-01-01

    Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, 'Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the 'teething' problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated 'mature' subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.

  13. Dispatchable Solar Power Plant Project

    Energy Technology Data Exchange (ETDEWEB)

    Price, Henry [Solar Dynamics LLC, Broomfield, CO (United States)

    2018-01-31

    As penetration of intermittent renewable power increases, grid operators must manage greater variability in the supply and demand on the grid. One result is that utilities are planning to build many new natural gas peaking power plants that provide added flexibility needed for grid management. This report discusses the development of a dispatchable solar power (DSP) plant that can be used in place of natural gas peakers. Specifically, a new molten-salt tower (MST) plant has been developed that is designed to allow much more flexible operation than typically considered in concentrating solar power plants. As a result, this plant can provide most of the capacity and ancillary benefits of a conventional natural gas peaker plant but without the carbon emissions. The DSP system presented was designed to meet the specific needs of the Arizona Public Service (APS) utility 2017 peaking capacity request for proposals (RFP). The goal of the effort was to design a MST peaker plant that had the operational capabilities required to meet the peaking requirements of the utility and be cost competitive with the natural gas alternative. The effort also addresses many perceived barriers facing the commercial deployment of MST technology in the US today. These include MST project development issues such as permitting, avian impacts, visual impacts of tower CSP projects, project schedule, and water consumption. The DSP plant design is based on considerable analyses using sophisticated solar system design tools and in-depth preliminary engineering design. The resulting DSP plant design uses a 250 MW steam power cycle, with solar field designed to fit on a square mile plot of land that has a design point thermal rating of 400 MWt. The DSP plant has an annual capacity factor of about 16% tailored to deliver greater than 90% capacity during the critical Arizona summer afternoon peak. The table below compares the All-In energy cost and capacity payment of conventional combustion turbines

  14. Operational aspects of the radiological control in a radioisotopes plant production

    International Nuclear Information System (INIS)

    Corahua, A.

    1996-01-01

    The purpose of this paper is to inform about the results obtained in the control operations carried out by the radioprotection area of the radioisotopes plant production during 1994 and then were compared with the limits established by the regulations of radiological radioprotection. In the general inter-texture of the activities that are developed in the radioisotopes plant production, the carried out controls are: area monitoring, air monitoring, personnel monitoring, monitoring in the expedition of radioactive material and monitoring and control in the evacuation of solid and liquid wastes. The result obtained in the present paper states that the doses received by the exposed occupationally staff are below the allowed limits. (author). 3 refs

  15. Atucha I nuclear power plant transients analysis

    International Nuclear Information System (INIS)

    Castano, J.; Schivo, M.

    1987-01-01

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

  16. Development of nuclear power plant Risk Monitor

    International Nuclear Information System (INIS)

    Yang Xiaoming; Sun Jinlong; Ma Chao; Wang Lin; Gu Xiaohui; Bao Zhenli; Qu Yong; Zheng Hao

    2014-01-01

    Risk Monitor is a tool to monitor the real-time risk of a nuclear power plant for risk management and comprehensive decision-making, which has been widely used all over the world. The nuclear power plant Risk Monitor applies the real-time risk model with low-complicacy that could reflect the plant's actual configuration, automatically reads the plant's configuration information from the engineering system through the developed interface, and efficiently analyzes the plant's risk Dy the intelligent parallel-computing method in order to provide the risk basement for the safety management of nuclear power plant. This paper generally introduces the background, architecture, functions and key technical features of a nuclear power plant Risk Monitor, and validates the risk result, which could well reflect the plant's risk information and has a significant practical value. (authors)

  17. Reliability of the emergency ac-power system at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

    1982-01-01

    The reliability of the emergency ac-power systems typical of several nuclear power plants was estimated, the costs of several possible improvements was estimated. Fault trees were constructed based on a detailed design review of the emergency ac-power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. It was found that there are not one or two improvements that can be made at all plants to significantly increase the industry-average emergency ac-power-system reliability, but the improvements are varied and plant-specific. Estimates of the improvements in reliability and the associated cost are estimated using plant-specific designs and failure probabilities

  18. The application of plant information system on third Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Liu Wangtian

    2005-01-01

    Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

  19. The atlas of large photovoltaic power plants

    International Nuclear Information System (INIS)

    Ducuing, S.; Guillier, A.; Guichard, M.A.

    2015-01-01

    This document reports all the photovoltaic power plants whose installed power is over 1 MWc and that are operating in France or in project. 446 power plants have been reviewed and their cumulated power reaches 2822 MWc. For each plant the following information is listed: the name of the municipality, the operator, the power capacity, the manufacturer of the photovoltaic panels and the type of technology used, the type of installation (on the ground, on the roof, on the facade, as sun protection,...), the yearly power output (kWh), and the date of commissioning. This review shows that 86% of these plants are ground-based. (A.C.)

  20. 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.

  1. AERIAL RADIOLOGICAL SURVEYS

    International Nuclear Information System (INIS)

    Proctor, A.E.

    1997-01-01

    Measuring terrestrial gamma radiation from airborne platforms has proved to be a useful method for characterizing radiation levels over large areas. Over 300 aerial radiological surveys have been carried out over the past 25 years including U.S. Department of Energy (DOE) sites, commercial nuclear power plants, Formerly Utilized Sites Remedial Action Program/Uranium Mine Tailing Remedial Action Program (FUSRAP/UMTRAP) sites, nuclear weapons test sites, contaminated industrial areas, and nuclear accident sites. This paper describes the aerial measurement technology currently in use by the Remote Sensing Laboratory (RSL) for routine environmental surveys and emergency response activities. Equipment, data-collection and -analysis methods, and examples of survey results are described

  2. Heat supply from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Stach, V [Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)

    1978-05-01

    The current state of world power production and consumption is assessed. Prognoses made for the years 1980 to 2000 show that nuclear energy should replace the major part of fossil fuels not only in the production of power but also in the production of heat. In this respect high-temperature reactors are highly prospective. The question is discussed of the technical and economic parameters of dual-purpose heat and power plants. It is, however, necessary to solve problems arising from the safe siting of nuclear heat and power plants and their environmental impacts. The economic benefits of combined power and heat production by such nuclear plants is evident.

  3. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  4. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  5. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    2000-08-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  6. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  7. Standard criteria for disposal of liquid radioactive wastes from nuclear power plants into surface waters (river systems)

    International Nuclear Information System (INIS)

    Pisarev, V.V.; Tsybizov, I.S.

    1976-01-01

    Radioactive products discharge into natural water streams results in the necessity to regulate nuclear power plant discharges to ensure radiation safety (RS) for population using a river and surrounding river territory. To ensure RS it is necessary to set scientific-founded standards of permissible discharge level of liquid radioactive wastes (LRW) from nuclear power plant assuring observance of hygienic requirements for surface water puring. Volume of permissible LRW discharge into river systems must be set both with provision for concrete physical-geographycal conditions, specficity of utilizing the river and river valley and social-economical peculiarities of crtical population groups. The value of permissible LRW discharge into river systems is determined by three criterion groups: radiological, ecological and hydrological ones. By means of radiological group the internal and external irradiation doses for the whole body and its separate organs are set and RS of population is determined. Ecological criteria include a number of parameters (coefficients of accumulation, distribution and transition) determining quantitative ratios between radioactive element contents in water and separate links of biological chains: soil/water, fish/water, vegetables/water and others. Hydrological criteria determine the degree of waste dilution in rivers, control radioactive contamination of flood-lands areas and in common with ecological criteria determine radionuclide contents in soil and food products. A method of determining average annual values of LRW dilution in river waters is presented [ru

  8. 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.)

  9. Technical report on dc power supplies in nuclear power plants

    International Nuclear Information System (INIS)

    1977-06-01

    Emergency electrical power supplies, both a.c. and d.c. for nuclear power plants are important to safety. For this reason, the electric power systems for operating nuclear plants and those plants under licensing review have been required to provide a high degree of reliability. It is this high reliability that provides confidence that sufficient safety margin exists against loss of all d.c. power for extended periods of time to allow an orderly examination of safety issues, such as this. However, because of the importance of the a.c. and d.c. power systems, the staff has been expending effort to review the reliability of these systems and shall continue to do so in the future

  10. Computerization of off-site dose calculations at two nuclear power plants

    International Nuclear Information System (INIS)

    Lei, W.; Robertson, C.E.; Moore, G.T.; Rawls, B.E.; Sipp, J.R.

    1988-01-01

    The Brunswick Nuclear Project (BNP) consists of two boiling water reactors designed to generate a total net output of 1642 MWe. Unit 2 achieved commercial production in 1975, and Unit 1 began commercial operation in 1977. The Harris nuclear Project (HNP) is an 860 MWe pressurized water reactor that entered commercial operation in May of 1987. both plant sites are operated by Carolina Power and Light Company (CP and L). During January 1984, BNP replaced its older effluent technical specifications (part of the plant's original license) with the newer generation of Radiological Effluent Technical Specifications (RETS) mandated by the U.S. Nuclear Regulatory Commission. The RETS for HNP were integrated directly into this initial technical specifications. The initial version of the ODCM for BNP was drafted by a vendor and then extensively rewritten by the plant staff. The manual for HNP was drafted by CP and L corporate staff. At the outset, it was realized how impractical it would be to attempt to manually perform all of the dose calculations and keep the necessary records. The alternative-computerization-required extensive in-plant and corporate efforts to identify the computing resources (hardware) needed, create the software for ODCM implementation, and test, verify, validate, and document the software. This paper discusses these efforts

  11. Net energy balance of tokamak fusion power plants

    International Nuclear Information System (INIS)

    Buende, R.

    1983-01-01

    The net energy balance for a tokamak fusion power plant of present day design is determined by using a PWR power plant as reference system, replacing the fission-specific components by fusion-specific components and adjusting the non-reactor-specific components to altered conditions. For determining the energy input to the fusion plant a method was developed that combines the advantages of the energetic input-output method with those of process chain analysis. A comparison with PWR, HTR, FBR, and coal-fired power plants is made. As a result the energy expenditures of the fusion power plant turn out to be lower than that of an LWR, HTR, or coal-fired power plant of equal net electric power output and nearly in the same range as FBR power plants. (orig.)

  12. Independent auto evaluation of an operative radiological protection program; Autoevaluacion independiente de un programa de proteccion radiologica operativa

    Energy Technology Data Exchange (ETDEWEB)

    Medrano L, M.A.; Rodriguez C, C.C.; Linares R, D.; Zarate M, N.; Zempoalteca B, R. [Gerencia Subsede Sureste Instituto Nacional de Investigaciones Nucleares, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: maam@nuclear.inin.mx

    2006-07-01

    The program of operative radiological protection of a nuclear power plant consists of multiple procedures and associate tasks that have as purpose the radiological protection of the workers of the power station. It is for this reason that the constant evaluation of the one it programs it is an important tool in the identification of their weaknesses (and strengths), so they can be assisted appropriately. In this work the main elements of the program of independent auto evaluation of the program of operative radiological protection of the Laguna Verde Central that has been developed and implemented by the National Institute of Nuclear Research are described. (Author)

  13. Radiological risk curves for the liquid radioactive waste transfer from Angra 1 to Angra 2 nuclear power plants by a container tank

    International Nuclear Information System (INIS)

    Alves, A.S.M.; Passos, E.M. dos; Duarte, J.P.

    2013-01-01

    Eletrobras Termonuclear has a radiowaste management program focused on reducing the produced volumes, for which it has considered to transfer Angra 1 liquid radioactive waste by a container tank to be processed and packed in Angra 2. This paper presents a radiological risk study for providing the necessary technical foundations to obtain the license from the regulatory agency for implementing this transfer operation. Out of the 92 accident scenarios identified with the help of a preliminary hazard analysis, the greatest risk of fatal cancer for members of the public was equal to 6.9 x 10 -13 fatalities/yr, which refers to the accident scenario involving intrinsic failures of valves, hoses, flanges, seals, gaskets and instrumentation lines, while filling the container tank at Angra 1 filling station. This risk figure is about ten million times less than the one adopted by Eletronuclear for such a waste transfer. The highest frequency was also associated with this type of scenario, and its value was equal to 1.4 x 10 -6 yr -1 . This paper also presents and discusses the radiological risk curves for the three possible in-plant transfer routes, the Angra 1 filling station and Angra 2 discharging station and the overall risk curve in order to allow for a broader perspective of the results obtained. These risk curves display the accident scenarios frequencies against radiation doses by considering relevant in-plant and surroundings release paths. In these curves, the extreme scenarios mentioned earlier can be clearly identified in terms of occurrence frequencies and radiation doses. (author)

  14. Operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Ackermann, G.

    1987-01-01

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

  15. Some lessons on radiological protection learnt from the accident at the Fukushima Dai-ichi nuclear power plant

    International Nuclear Information System (INIS)

    Kai, M

    2012-01-01

    The accident at the Fukushima Dai-ichi nuclear power plant released a large quantity of radioactive iodine and caesium into the environment. In terms of radiological protection, the evacuation and food restrictions that were adopted in a timely manner by the authorities effectively reduced the dose received by people living in the affected area. Since late March, the transition from an emergency to an existing exposure situation has been in progress. In selecting the reference exposure levels in some areas under an existing exposure situation, the authorities tried to follow the situation-based approach recommended by the ICRP. However, a mixture of emergency and post-emergency approaches confused the people living in the contaminated areas because the reactor conditions continued to be not completely stable. In deriving the criteria in an existing exposure situation, the regulatory authority selected 20 mSv y −1 . The mothers in the affected area believed that a dose of 20 mSv y −1 was unacceptably high for children since 1 mSv y −1 is the dose limit for the public under normal conditions. Internet information accelerated concern about the internal exposure to children and the related health effects. From some experiences after the accident the following lessons could be learned. The selection of reference doses in existing exposure situations after an accident must be openly communicated with the public using a risk-informed approach. The detriment-adjusted nominal risk coefficient was misused for calculating the hypothetical number of cancer deaths by some non-radiation experts. It would not be possible to resolve this problem unless the ICRP addressed an alternative risk assessment to convey the meaning and associated uncertainty of the risk to an exposed population. A situation-based approach in addition to a risk-informed approach needs to be disseminated properly in order to select the level of protection that would be the best possible under the

  16. Power plant conceptual studies in Europe

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  17. Chemistry management system for nuclear power plants

    International Nuclear Information System (INIS)

    Nagasawa, Katsumi; Maeda, Katsuji

    1998-01-01

    Recently, the chemistry management in the nuclear power plants has been changing from the problem solution to the predictive diagnosis and maintenance. It is important to maintain the integrity of plant operation by an adequate chemistry control. For these reasons, many plant operation data and chemistry analysis data should be collected and treated effectively to evaluate chemistry condition of the nuclear power plants. When some indications of chemistry anomalies occur, quick and effective root cause evaluation and countermeasures should be required. The chemistry management system has been developed as to provide sophisticate chemistry management in the nuclear power plants. This paper introduces the concept and functions of the chemistry management system for the nuclear power plants. (author)

  18. Nuclear power plant safety

    International Nuclear Information System (INIS)

    Otway, H.J.

    1974-01-01

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

  19. Modeling of the wind power plant using software DIgSILENT Power factory

    International Nuclear Information System (INIS)

    Mladenovski, Ljubisha; Iliev, Atanas; Fushtikj, Vangel

    2004-01-01

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

  20. Preparation and practice for nuclear power plant operation

    International Nuclear Information System (INIS)

    Wu Xuesong; Lu Tiezhong

    2015-01-01

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

  1. Simulation technology for power plants

    International Nuclear Information System (INIS)

    Kuwabara, Kazuo; Yanai, Katsuya.

    1988-01-01

    In the simulation of nuclear power stations, there are the simulation for the training of plant operation, the plant simulation for analyzing the operation of an electric power system, the simulation for controlling a core, the simulation for the safety analysis of reactors, the simulation for the design analysis of plants and so on as the typical ones. The outline and the technical features of these simulations are described. With the increase of capacity and complexity of thermal power plants, recently the automation of operation has advanced rapidly. The chance of starting up and stopping plants by operators themselves is few, and the chance of actually experiencing troubles also is few as the reliability of plants improved. In order to maintain the ability of coping with plant abnormality, an operation supporting system is strongly demanded. Operation training simulators and used widely now, and there are the simulators for analysis, those of replica type, those of versatile compact type and so on. The system configuration, modeling techniques, training function and others of the replica type are explained. In hydroelectric plants, the behavior of water in penstocks, the characteristics of water turbines, the speed control system for water turbines and the characteristics of generators become the main subjects of simulation. These are described. (Kako, I.)

  2. Nuclear power plant steam pipes repairing with TIRANT 3 robot system

    International Nuclear Information System (INIS)

    Soto Tomas, Marcelo; Curiel Nieva, Marceliano; Monzo Blasco, Enrique; Rodriguez, Salvador Pineda; Vaquer Perez, Juan I.

    2011-01-01

    A typical application functions covering the steam pipes inner surface in coal-fired power station and nuclear power plants. The results of this process are spectacular in terms of protection against corrosion and abrasion, but its application has conditioning factors, such as: Severe application conditions for workers. Due to the postural position (usually kneeling) in small diameter pipes and working with fireproof clothing and masks with outdoor air supplying, due to fumes, sparks and molten metal particles, radiological contamination, confined space, poor lighting... Coating uniformity. As metallization is a manual process, the carried out measurements show small variations in the thickness of the coating, always within the tolerance limits established by the applicable regulations and quality assurance. For all these reasons, Grupo Dominguis has developed the TIRANT 3 robot, a worldwide innovative system, for metallization of steam pipes inner surface. TIRANT 3 robot is teleoperated from outside of the pipe, so that human intervention is reduced to the operations of robot positioning and change of metallization wire. As it is an independent system of the human factor, metallization process performance is significantly increased by reducing rest periods due only to the robot maintenance. Likewise, TIRANT 3 system permits to increase resulting coating uniformity, and thus its resistance, keeping selected parameters constant depending on required type and thickness of wire. TIRANT 3 system has successfully worked in 2010 during the stops refueling of the Units I and II of Laguna Verde nuclear power plant in Mexico. (author)

  3. Current fusion power plant design concepts

    International Nuclear Information System (INIS)

    Gore, B.F.; Murphy, E.S.

    1976-09-01

    Nine current U.S. designs for fusion power plants are described in this document. Summary tabulations include a tenth concept, for which the design document was unavailable during preparation of the descriptions. The information contained in the descriptions was used to define an envelope of fusion power plant characteristics which formed the basis for definition of reference first commercial fusion power plant design. A brief prose summary of primary plant features introduces each of the descriptions contained in the body of this document. In addition, summary tables are presented. These tables summarize in side-by-side fashion, plant parameters, processes, combinations of materials used, requirements for construction materials, requirements for replacement materials during operation, and production of wastes

  4. Occupational exposure trend and the radiological protection optimization criteria in Spanish nuclear power plants in operation: present and future

    International Nuclear Information System (INIS)

    O'Donnell, P.

    1992-01-01

    Occupational collective dose per reactor evolution in the operating nuclear power plants in Spain has shown in the last years a tendency to stability, within a range of values similar to the average of the OECD countries. On the other hand, the last ICRP's recommendations will support a further effort for utilities and external contractors in order to adapt to the new individual dose limits. The lecturer considers that Spain must not accommodate to the present situation and should continue developing the ALARA criteria in its nuclear power plants. In this presentation the main indicators to assess the present development level of this criteria are reviewed and the basis to improve the effectiveness of the practical application of it is proposed. (author)

  5. Net energy balance of tokamak fusion power plants

    International Nuclear Information System (INIS)

    Buende, R.

    1981-10-01

    The net energy balance for a tokamak fusion power plant was determined by using a PWR power plant as reference system, replacing the fission-specific components by fusion-specific components and adjusting the non-reactor-specific components to altered conditions. For determining the energy input to the fusion plant a method was developed that combines the advantages of the energetic input-output method with those of process chain analysis. A comparison with PWR, HTR, FBR, and coal-fired power plants is made. As a result the net energy balance of the fusion power plant turns out to be more advantageous than that of an LWR, HTR or coal-fired power plant and nearly in the same range as FBR power plants. (orig.)

  6. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-02-01

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

  7. Italian steam power plants

    Energy Technology Data Exchange (ETDEWEB)

    von Rautenkranz, J

    1939-01-01

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

  8. 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.)

  9. 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.)

  10. 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

  11. Effect of special features of nuclear power plants

    International Nuclear Information System (INIS)

    Scharf, H.

    1986-01-01

    Special features of nuclear power plants are reported with the Muelheim-Kaerlich pressurized water reactor as the reference plant. This nuclear reactor uses 'Once Through Steam Generators (OTSG)' with 'Integrated Economizer' to provide the turbine with superheated steam. The implementation of OTSG allows to operate the plant with constant steam pressure over the entire power range, and with constant main coolant temperature over a power range from 15% power to 100% power. Control of the plant during power operation is provided by the 'Integrated Control System', which simultaneously sends signals to the plant's subsystems reactor, OTSG, and turbine to get optimum response of the plant during power transients. The characteristics of this 'Integrated Control System' and its different modes of operation are presented. (orig./GL)

  12. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    Wood, R.S.

    1979-12-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of December 1, 1979. The list includes all plants licensed to operate, under construction, docketed for NRC safety and envionmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally cancelled. In many cases, ownership may be in the process of changing as a result of antitrust license conditions and hearings, altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified

  13. Risks and consequences of a hypothetical radiological accident on nuclear powered submarine traversing Suez canal

    International Nuclear Information System (INIS)

    Salama, Mohamed

    2008-01-01

    Full text: Egypt has unique problem in Suez Canal, although there are, a number of radioactive Cargos traveling through the Canal which includes new and spent reactor fuel and about 100 metric tons of uranium hexafluoride each year, under the regulatory control of the Egyptian Atomic Energy Authority, there is, still a major problem concerning the passage of a number of nuclear powered vessels and submarines passing through the canal several times each year. The passage of these vessels and submarines has a political situation and not under the regulatory control of the Egyptian regulatory body. In spite of all precautions that are taken, in the nuclear powered vessels and submarines from the point of view of the rugged design of the reactor plant, multiple safety systems and operation with exceptional consideration for safety. Although of all of these a potential for a serious accident may does arise, even though, its probability is minimal. The Government of Egypt has established a national radiological emergency plan in order to cope with any radiological accidents, which may arise inside the country. Suez Canal lies in the north east of Egypt, and passes through a zone of considerable business, agriculture and industrial activities. The zone consists of three populated provinces, Port Said, Ismailia and Suez. According to Suez Canal authority regulations it is not allowed for these vessels and submarines to be landed in port. The motivation of the present paper was undertaken to discuss a hypothetical nuclear reactor accident aboard a nuclear powered submarine occurred during its passage in the Suez Canal. Such an accident will produce a radioactive cloud containing a number of radioactive materials. In such type of accidents contamination and causality zones, could extend to several kilometers. The different phases of the accident are going to be discussed and analyzed. The emergency actions taken during the accident phases are going to be presented. The

  14. Nuclear and thermal power plants and the environment

    International Nuclear Information System (INIS)

    Mejstrik, V.

    1978-01-01

    The growth is briefly outlined of world daily power consumption and the possibilities are discussed of meeting this demand. Coal and nuclear power are of primary importance as energy resources for the present and the near future. Production costs per 1 kWh of electric power in nuclear power plants are already lower in fossil fuel power plants and both types of power plants have an environmental impact. Activities are presented of radioisotopes resulting from nuclear reactor operation and their release and environmental impact are discussed. An analysis is made of emissions from combustion processes and of wastes from fossil-fuel power plant operation. The environmental impacts of nuclear and fossil fuel power plants are compared. (Z.M.)

  15. Nuclear and thermal power plants and the environment

    Energy Technology Data Exchange (ETDEWEB)

    Mejstrik, V [Ceskoslovenska Akademie Ved, Pruhonice. Ustav Krajinne Ekologie

    1978-01-01

    The growth is briefly outlined of world daily power consumption and the possibilities are discussed of meeting this demand. Coal and nuclear power are of primary importance as energy resources for the present and the near future. Production costs per 1 kWh of electric power in nuclear power plants are already lower than in fossil fuel power plants and both types of power plants have an environmental impact. Activities are presented of radioisotopes resulting from nuclear reactor operation and their release and environmental impact are discussed. An analysis is made of emissions from combustion processes and of wastes from fossil-fuel power plant operation. The environmental impacts of nuclear and fossil fuel power plants are compared.

  16. The safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    Do nuclear power plants present an unjustifiable risk Can there be confidence in their safety The Uranium Institute invited a group of senior safety experts from eight different Western countries operating different types of reactors to provide an authoritative explanation for non-specialists of the basic principles of reactor safety, their application and their implications. The report presents the group's opinion on the level of safety achieved in the Western nuclear power plants with which the authors are directly familiar. Although many of the points made may well also be true for non-Western reactors, the report does not cover them except where specifically stated. It does describe and discuss the causes of the Chernobyl disaster. It does not compare nuclear power with other fuels, nor does it deal with its benefits, since however great the benefits from the peaceful use of nuclear power, and its own advantages over other fuels, they could not compensate for lack of safety. The conclusion reached is that the risk associated with electricity production at nuclear power plants can be kept very low. Proper use of the extensive knowledge available today can guarantee operation of nuclear power plants at very high safety levels, carrying very low risks, both to health and of contamination of the environment: risks that are continually lowered by upgrading existing plants and their operation, and by the design of future power plants. (author).

  17. DENINT power plant cost benefit analysis code: Analysis of methane fuelled power plant/district heating system

    International Nuclear Information System (INIS)

    Cincotti, V.; D'Andrea, A.

    1989-07-01

    The DENINT power plant cost benefit analysis code takes into consideration, not only power production costs at the generator terminals, but also, in the case of cogeneration, the costs of the fuel supply and heat and power distribution systems which depend greatly on the location of the plant. The code is able to allow comparisons of alternatives with varying annual operation hours, fuel cost increases, and different types of fossil fuels and production systems. For illustrative purposes, this paper examines two methane fired cogeneration plant/district heating alternatives

  18. Energy analysis and projecting of power plants

    International Nuclear Information System (INIS)

    Jirlow, K.

    1975-01-01

    Energy analysis aims at a better explanation of energy flow and energy exchange at different production processes. In this report the energy budget is analysed for separate nuclear power plants and for expanding systems of power plants. A mathematical model is developed for linear and exponential expanding of nuclear power. The profitableness for nuclear power plants in Sweden is considered to be good. (K.K.)

  19. Guinea_WADC00321_ADBG_Guinea_Power_Plants

    Data.gov (United States)

    United Nations Cartographic Section — Data for power plants with total installed generating capacity > 10 mw from the Platts World Electric Power Plants Database (WEPP 2006). Plants were georeferenced...

  20. Commissioning of the nuclear power plant

    International Nuclear Information System (INIS)

    Furtado, P.M.; Rolf, F.

    1984-01-01

    Nuclear Power Plant Angra 2, located at Itaorna Beach-Angra dos Reis is the first plant of the Brazilian-German Agreement to be commissioned. The Nuclear Power Plant is a pressurized water reactor rated at 3765 Mw thermal/1325 Mw electrical. For commissioning purpose the plant is divided into 110 systems. Plant commissioning objective is to demonstrate the safe and correct operation of each plan component, system and of the whole plant in agreement with design conditions, licensing requirements and contractual obligations. This work gives a description of plant commissioning objectives, activities their time sequence, and documentation. (Author) [pt

  1. Radiological Consequences Analysis for Abnormal Condition on NPPs 1000 MWe by Using Radcon Model

    International Nuclear Information System (INIS)

    Pande Mande Udiyani; Sri Kuntjoro

    2009-01-01

    The operation of NPPs (Nuclear Power Plants) in Indonesia to anticipates rare of energy will generate various challenges, especially about NPPs safety. So installation organizer of nuclear must provide scientific argument to safety NPPs, one of them is by providing document of safety analysis. Calculation of radiological consequences after abnormal condition applies on generic PWR-1000 power reactor. Calculation is done by using program package RadCon (Radiological Consequences Model), with postulate condition is based on DBA (Design Basis Accident). Calculation of dispersion of radionuclide concentration is using PC-COSYMA as input data for RadCon. Simulation for radiological consequences analysis uses by site data sample. Analysis result shows that maximum receiving of internal - externals radiological consequence for short term and long-term below 1 km radius area is below the limit acceptably effective dose for a member of the public as a result of an accident which should not exceed 5 mSv (ICRP 1990). (author)

  2. Current production costs in various power plant systems

    Energy Technology Data Exchange (ETDEWEB)

    Weible, H.

    1977-01-01

    The costs of producing electric power were evaluated for flowing water power plants, storage and pumped storage power plants, bituminous coal power plants, heating oil power plants (fired with heavy heating oil), natural gas-fired power plants, gas turbines, pressurized water reactors, and boiling water reactors. The calculational methods used for evaluating costs and the input data for methods used for the KOSKON and KOSKERN computer programs are described. It is emphasized that the calculations are examples to indicate the possible effects of the cost program and are only as valid as the input data. (JSR)

  3. Water regime of steam power plants

    International Nuclear Information System (INIS)

    Oesz, Janos

    2011-01-01

    The water regime of water-steam thermal power plants (secondary side of pressurized water reactors (PWR); fossil-fired thermal power plants - referred to as steam power plants) has changed in the past 30 years, due to a shift from water chemistry to water regime approach. The article summarizes measures (that have been realised by chemists of NPP Paks) on which the secondary side of NPP Paks has become a high purity water-steam power plant and by which the water chemistry stress corrosion risk of heat transfer tubes in the VVER-440 steam generators was minimized. The measures can also be applied to the water regime of fossil-fired thermal power plants with super- and subcritical steam pressure. Based on the reliability analogue of PWR steam generators, water regime can be defined as the harmony of construction, material(s) and water chemistry, which needs to be provided in not only the steam generators (boiler) but in each heat exchanger of steam power plant: - Construction determines the processes of flow, heat and mass transfer and their local inequalities; - Material(s) determines the minimal rate of general corrosion and the sensitivity for local corrosion damage; - Water chemistry influences the general corrosion of material(s) and the corrosion products transport, as well as the formation of local corrosion environment. (orig.)

  4. Methodology used by the spanish nuclear regulatory body in the radiological impact assessment

    International Nuclear Information System (INIS)

    Diaz de la Cruz, F.

    1979-01-01

    The radiological risk assessment derived from the operation of a nuclear power plant is done in Spain with methods taken basically from the U.S.N.R.C. regulatory guides. This report presents the way followed by the Spanish Regulatory Body in order to arrive to an official decision on the acceptability of a nuclear plant in the different steps of the licensing. (author)

  5. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Essmann, J.

    1981-01-01

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

  6. Power system stabilising features from wind power plants augmented with energy storage

    DEFF Research Database (Denmark)

    Tarnowski, Germán C.; Kjær, Philip C; Lærke, Rasmus

    2014-01-01

    This paper describes a wind power plant augmented with energy storage, configured to provide ancillary services (primary reserve, inertial response, power oscillation damping) for enhancement of power system stability. Energy storage can complement wind power plants thus reducing the need for any...... overload or curtailment to allow active power modulation. A 12MW + 1.6MW augmented plant is used for demonstration of representative performance of the particular ancillary service control algorithms...

  7. Cooling towers for thermal power plants

    International Nuclear Information System (INIS)

    Chaboseau, J.

    1987-01-01

    After a brief recall on cooling towers testing and construction, this paper presents four examples of very large French nuclear power plant cooling towers, and one of an Australian thermal power plant [fr

  8. Simulation of ¹³⁷Cs transport and deposition after the Chernobyl Nuclear Power Plant accident and radiological doses over the Anatolian peninsula.

    Science.gov (United States)

    Simsek, V; Pozzoli, L; Unal, A; Kindap, T; Karaca, M

    2014-11-15

    The Chernobyl Nuclear Power Plant (CNPP) accident occurred on April 26 of 1986, it is still an episode of interest, due to the large amount of radionuclides dispersed in the atmosphere. Caesium-137 ((137)Cs) is one of the main radionuclides emitted during the Chernobyl accident, with a half-life of 30years, which can be accumulated in humans and animals, and for this reason the impacts on population are still monitored today. One of the main parameters in order to estimate the exposure of population to (137)Cs is the concentration in the air, during the days after the accident, and the deposition at surface. The transport and deposition of (137)Cs over Europe occurred after the CNPP accident has been simulated using the WRF-HYSPLIT modeling system. Four different vertical and temporal emission rate profiles have been simulated, as well as two different dry deposition velocities. The model simulations could reproduce fairly well the observations of (137)Cs concentrations and deposition, which were used to generate the 'Atlas of Caesium deposition on Europe after the Chernobyl accident' and published in 1998. An additional focus was given on (137)Cs deposition and air concentrations over Turkey, which was one of the main affected countries, but not included in the results of the Atlas. We estimated a total deposition of 2-3.5 PBq over Turkey, with 2 main regions affected, East Turkey and Central Black Sea coast until Central Anatolia, with values between 10 kBq m(-2) and 100 kBq m(-2). Mean radiological effective doses from simulated air concentrations and deposition has been estimated for Turkey reaching 0.15 mSv/year in the North Eastern part of Turkey, even if the contribution from ingestion of contaminated food and water is not considered, the estimated levels are largely below the 1 mSv limit indicated by the International Commission on Radiological Protection. Copyright © 2014 Elsevier B.V. All rights reserved.

  9. Permanent cessation of Tokai power plant's operation

    International Nuclear Information System (INIS)

    Satoh, T.

    1998-01-01

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

  10. Vibrations of wind power plants; Schwingungen von Windenergieanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    Within the meeting of the department vibration engineering of the Association of German Engineers (Duesseldorf, Federal Republic of Germany) between 3rd and 4th February, 2010 in Hanover (Federal Republic of Germany) the following lectures are presented: (1) Reduction of forced strengths generated by wagging and snaking of the rotor in the power strain of wind power plants (F. Mitsch); (2) Reduction of vibrations at wind power plants by means of active additional systems (S. Katz, S. Pankoke, N. Loix); (3) Reduction of vibrations by means of balancing and alignment (E. Becker, M. Kenzler); (4) Active absorber for reducing tonal emissions of vibration at wind power plants (R. Neugebauer, M. Linke, H. Kunze, M. Ulrich); (5) Control structures for damping torsion vibrations and peak loads in the power strain of wind power converters (C. Sourkounis); (6) Possibilities of a non-contact investigation of vibrations at wind power plants (R. Behrendt, E. Reimers, H. Wiegers); (7) Influences on the loadability of CMS statements (R. Wirth); (8) Recording modal structural properties with sensor grids and methods of operational modal analysis (A. Friedmann, D. Mayer, M. Koch, M. Kauba, T. Melz); (9) Early failure detection of damages of roller bearings in wind power gear units with variable speed (B. Hacke, G. Poll); (10) Condition monitoring in wind power plants - structure monitoring and life time monitoring of wind power plants (SCMS and LCMS) (H. Lange); (11) Development of a model-based structural health monitoring system for condition monitoring of rotor blades (C. Ebert, H. Friedmann, F.O. Henkel, B. Frankenstein, L. Schubert); (12) Efficient remote monitoring at wind power plants by means of an external diagnosis centre (G. Ceglarek); (13) Accurate turbine modelling at component and assembly level for durability and acoustic analysis (D. v. Werner, W. Hendricx); (14) Possibilities of the investigation of the dynamic behaviour of power strains in wind power plants by

  11. Power plants and safety 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The papers of this volume deal with the whole range of safety issues from planning and construction to the operation of power plants, and discuss also issues like availability and safety of power plants, protective clothes and their incommodating effect, alternatives for rendering hot-water generators safe and the safety philosophy in steam turbine engineering. (HAG) [de

  12. China’s Nuclear Power Plants in Operation

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

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

  13. 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

  14. Public exposure from environmental release of radioactive material under normal operation of unit-1 Bushehr nuclear power plant

    International Nuclear Information System (INIS)

    Sohrabi, M.; Parsouzi, Z.; Amrollahi, R.; Khamooshy, C.; Ghasemi, M.

    2013-01-01

    Highlights: ► The unit-1 Bushehr nuclear power plant is a VVER type reactor with 1000 MWe power. ► Doses of public critical groups living around the plant were assessed under normal reactor operation conditions. ► PC-CREAM 98 computer code developed by the HPA was applied to assess the public doses. ► Doses are comparable with those in the FSAR, in the ER and doses monitored. ► The doses assessed are lower than the dose constraint of 0.1 mSv/y associated with the plant. - Abstract: The Unit-1 Bushehr Nuclear Power Plant (BNPP-1), constructed at the Hallileh site near Bushehr located at the coast of the Persian Gulf, Iran, is a VVER type reactor with 1000 MWe power. According to standard practices, under normal operation conditions of the plant, radiological assessment of atmospheric and aquatic releases to the environment and assessment of public exposures are considered essential. In order to assess the individual and collective doses of the critical groups of population who receive the highest dose from radioactive discharges into the environment (atmosphere and aquatic) under normal operation conditions, this study was conducted. To assess the doses, the PC-CREAM 98 computer code developed by the Radiation Protection Division of the Health Protection Agency (HPA; formerly called NRPB) was applied. It uses a standard Gaussian plume dispersion model and comprises a suite of models and data for estimation of the radiological impact assessments of routine and continuous discharges from an NPP. The input data include a stack height of 100 m annual radionuclides release of gaseous effluents from the stack and liquid effluents that are released from heat removal system, meteorological data from the Bushehr local meteorological station, and the data for agricultural products. To assess doses from marine discharges, consumption of sea fish, crustacean and mollusca were considered. According to calculation by PC-CREAM 98 computer code, the highest individual

  15. Plant life extensions for German nuclear power plants? Controversial discussion profit taking of nuclear power plant operators

    International Nuclear Information System (INIS)

    Matthes, Felix C.

    2009-10-01

    The discussion on the plant life extensions for German nuclear power plants beyond the residual quantity of electricity particularly focus on three aspects: Effects for the emission of carbon dioxide as a greenhouse gas; Development of the electricity price for which a reduction or attenuation is postulated due to a plant life extension; Skimming of additional profits at operating companies and their use in the safeguarding of the future (development of renewable energies, support of energy efficiency, promotion of the research, consolidation of the public budget, and so on). Under this aspect, the author of the contribution under consideration reports on the profit taking of nuclear power plant operators. The presented analysis considers three aspects: (a) Specification of the quantity structures for the investigated model of plant life extension; (b) The decisive parameter is the revenue situation and thus the price development for electricity at wholesale markets; (c) Determination and evaluation of the course in time of the profit taking.

  16. Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

    International Nuclear Information System (INIS)

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

  17. Nuclear Plant Analyzer: an interactive TRAC/RELAP Power-Plant Simulation Program

    International Nuclear Information System (INIS)

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.; Mahaffy, J.; Turner, M.; Wiley, R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

  18. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

  19. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

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

    Science.gov (United States)

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

    2018-03-01

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

  1. TVA's nuclear power plant experience

    International Nuclear Information System (INIS)

    Willis, W.F.

    1979-01-01

    This paper reviews TVA's nuclear power plant design and construction experience in terms of schedule and capital costs. The completed plant in commercial operation at Browns Ferry and six additional plants currently under construction represent the nation's largest single commitment to nuclear power and an ultimate investment of $12 billion by 1986. The presentation is made in three separate phases. Phase one will recapitulate the status of the nuclear power industry in 1966 and set forth the assumptions used for estimating capital costs and projecting project schedules for the first TVA units. Phase two describes what happened to the program in the hectic early 1979's in terms of expansion of scope (particularly for safety features), the dramatic increase in regulatory requirements, vendor problems, stretchout of project schedules, and unprecedented inflation. Phase three addresses the assumptions used today in estimating schedules and plant costs for the next ten-year period

  2. Economic analysis of power generation from floating solar chimney power plant

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  3. Owners of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, C.R.; White, V.S.

    1996-11-01

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

  4. Bidding Strategy of Virtual Power Plant with Energy Storage Power Station and Photovoltaic and Wind Power

    Directory of Open Access Journals (Sweden)

    Zhongfu Tan

    2018-01-01

    Full Text Available For the virtual power plants containing energy storage power stations and photovoltaic and wind power, the output of PV and wind power is uncertain and virtual power plants must consider this uncertainty when they participate in the auction in the electricity market. In this context, this paper studies the bidding strategy of the virtual power plant with photovoltaic and wind power. Assuming that the upper and lower limits of the combined output of photovoltaic and wind power are stochastically variable, the fluctuation range of the day-ahead energy market and capacity price is stochastically variable. If the capacity of the storage station is large enough to stabilize the fluctuation of the output of the wind and photovoltaic power, virtual power plants can participate in the electricity market bidding. This paper constructs a robust optimization model of virtual power plant bidding strategy in the electricity market, which considers the cost of charge and discharge of energy storage power station and transmission congestion. The model proposed in this paper is solved by CPLEX; the example results show that the model is reasonable and the method is valid.

  5. Water - The radiological health of rivers: releases are very much controlled downstream power plants. What do hospital releases represent? The Seine reserves a surprise

    International Nuclear Information System (INIS)

    Anon.

    2015-01-01

    After a brief presentation of the role of the IRSN in the control of the radioactivity present in waters and in the control and follow-up of all sources of radioactivity, a first article briefly present the hydro-collector network, indicates that some point samplings of sediment and aquatic species are performed, that a national network of beacons for a continuous radioactivity measurement is installed in the main French rivers, downstream nuclear installations, and that advanced measurement techniques are used to detect very small level of tritium. Maps giving a brief indication of the radiological condition of the Loire and Rhone are provided. A second article addresses the control of releases downstream power plants, and evokes the legal context and the associated objectives and produced documents. The third article discusses the risk associated with hospital wastes and releases (liquid and solid effluents), how radioactivity is controlled between the hospital and tap water distribution. The last article reports and comments the results obtained by an analysis of historical pollutions trapped in the sediments of the Seine: 40 year-old traces of plutonium have been discovered, due to an accidental release from a CEA installation in Fontenay-aux-Roses, with no detrimental impact on population or on sewer workers

  6. Proceedings: Power Plant Electric Auxiliary Systems Workshop

    International Nuclear Information System (INIS)

    1992-06-01

    The EPRI Power Plant Electric Auxiliary Systems Workshop, held April 24--25, 1991, in Princeton, New Jersey, brought together utilities, architect/engineers, and equipment suppliers to discuss common problems with power plant auxiliary systems. Workshop participants presented papers on monitoring, identifying, and solving problems with auxiliary systems. Panel discussions focused on improving systems and existing and future plants. The solutions presented to common auxiliary system problems focused on practical ideas that can enhance plant availability, reduce maintenance costs, and simplify the engineering process. The 13 papers in these proceedings include: Tutorials on auxiliary electrical systems and motors; descriptions of evaluations, software development, and new technologies used recently by electric utilities; an analysis of historical performance losses caused by power plant auxiliary systems; innovative design concepts for improving auxiliary system performance in future power plants

  7. Intelligent power plant simulator for educational purposes

    International Nuclear Information System (INIS)

    Seifi, A.; Seifi, H.; Ansari, M. R.; Parsa Moghaddam, M.

    2001-01-01

    An Intelligent Tutoring System can be effectively employed for a power plant simulator so that the need for instructor in minimized. In this paper using the above concept as well as object oriented programming and SIMULINK Toolbox of MATLAB, an intelligent tutoring power plant simulator is proposed. Its successful application on a typical 11 MW power plant is demonstrated

  8. Reliability analysis techniques in power plant design

    International Nuclear Information System (INIS)

    Chang, N.E.

    1981-01-01

    An overview of reliability analysis techniques is presented as applied to power plant design. The key terms, power plant performance, reliability, availability and maintainability are defined. Reliability modeling, methods of analysis and component reliability data are briefly reviewed. Application of reliability analysis techniques from a design engineering approach to improving power plant productivity is discussed. (author)

  9. 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)

  10. Development of Air Dispersion Modeling for Future Nuclear Plant in Malaysia

    International Nuclear Information System (INIS)

    Mohd Nahar Othman

    2011-01-01

    The impact development of Nuclear power plant in Malaysia, can be very negative to the nearby population, causing public restlessness and consequently affecting the image of the authorities in the countries. The precise source of the pollution from the nuclear power plant must be determined, pollution emission level and the meteorological conditions are needed to predict and established the ambient air to the save level at the perimeter fence of the plant and address it with respect to the radiological ambient standards. Upon modeling using an established package as well as site measurements, the radiological level at the perimeter fence of the plant must deduced and lower than the normal ambient level. Based on this issue, a modeling study was made in vicinity of Malaysian Nuclear Agency TRIGA reactor in the area of Bangi, Selangor to evaluate the possibility of movement of air around the area and their impact. This paper will address and discuss the modeling base on the data getting from Meteorological Department such as measurement of wind speed, temperature, humidity, ambient air radiological concentration and ect. The purpose of Air Dispersion Modeling is to establish the critical ambient emission level, as well as radiological modeling. The focus will be made on exploring the use of Ausplume modeling to develop correlations between the radiological concentrations, chemical compositions and ambient model for emission controls. (author)

  11. Power from waste. [Power plant at landfill site

    Energy Technology Data Exchange (ETDEWEB)

    Anon,

    1991-01-01

    Base Load Systems Ltd, a company in the United Kingdom, has just commissioned a power plant in Leicestershire which uses waste gases from a landfill site. The gases power two specially modified turbo charged engine and generator packages. The plant will use approximately 100 cu meters of landfill gas per hour and is expected to feed 1.5MW of electrical power into the supply network of East Midlands Electricity. Once the landfill site has been completely filled and capped with clay, it is estimated that the electrical power output will be 4 MW. At present, since their are no customers for heat in the vicinity, 100 KW of the electricity produced are used to run fans to dissipate the 2.5 MW of waste heat. Base load is also involved elsewhere in combined heat and power projects. (UK).

  12. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1976-01-01

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  13. Radiological and chemical characterization report for the planned Quarry Construction Staging Area and Water Treatment Plant: Revision 1

    International Nuclear Information System (INIS)

    1989-03-01

    The Quarry Construction Staging Area and Water Treatment Plant (QCSA) will be used in the support of the bulk waste removal of the Weldon Spring Quarry. Radiological and chemical characterization was performed on a 12 acre site where the QCSA will be constructed. The characterization revealed approximately .5 acres of radiologically contaminated land. No chemical contamination was found. 8 refs., 5 figs., 7 tabs

  14. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.

    1992-01-01

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

  15. The plant efficiency of fusion power stations

    International Nuclear Information System (INIS)

    Darvas, J.; Foerster, S.

    1976-01-01

    Due to the circulating energy, lower efficiencies are to be expected with fusion power plants than with nuclear fission power plants. According to the systems analysis, the mirror machine is not very promising as a power plant. The plant efficiency of the laser fusion strongly depends on the laser efficiency about which one can only make speculative statements at present. The Tokamak requires a relatively low circulating energy and is certainly able to compete regarding efficiency as long as the consumption time can be kept large (> 100 sec) and the dead time between the power pulses small ( [de

  16. Tasks of a power engineer in future thermal power plants

    International Nuclear Information System (INIS)

    Freymeyer, P.; Scherschmidt, F.

    1982-01-01

    Today already the power plants provide plenty of tasks and problems to the electrical engineer in the fields of power and conductive engineering. A completely new orientation of power engineering leads to larger, more complex system and even to systems unknown so far. In conductive engineering entirely new solutions have come in view. There are a lot of interesting topics for the electrical engineer in the rearrangement and advance into virgin territory of thermal power plants. (orig.) [de

  17. Radiological assessment of radioactive contamination on private clothing

    International Nuclear Information System (INIS)

    Schartmann, F.; Thierfeldt, S.

    2003-01-01

    In the very rare, cases where private clothing of persons working in a nuclear installation are inadvertently contaminated and this contamination is not detected when leaving the facility, there may be radiological consequences for this person as well as for members of his or her family. The VGB (Technische Vereinigung der Grosskraftwerksbetreiber) in Germany has investigated in detail the spread of contamination in nuclear power plants. Part of this evaluation programme was a radiological analysis which has been carried out by Brenk Systemplanung GmbH (Aachen/Germany). The radiological analysis started with the definition of the source term. It is highly unlikely that activities of more than 5 kBq 60 Co could leave a plant undetected on the body or the clothes. Nevertheless activities up to 50 kBq and different nuclide vectors were regarded. It has been found that 60 Co is the most important contaminant. The radiological analysis focusses on two types of contamination: particles and surface contamination. The pathways by which such a contamination can lead to an exposure by external irradiation or by ingestion depend on the type of contamination and are analysed in detail. For example, a particle could be retained in pockets or other parts of clothing and may lead to prolonged external irradiation until the piece of clothing is washed. The analysis is performed on the basis of conservative to realistic assumptions. In conclusion, the analysis has shown that especially particle contamination needs to be focussed on. However, by the advanced detection equipment in German plants doses which may pose a health hazard can safely be excluded. (authors)

  18. Prospects for power plant technology

    International Nuclear Information System (INIS)

    Schilling, H.D.

    1993-01-01

    Careful conservation of resources in the enlarged context of the rational utilization of energy, the environment and capital will determine future power plant technology. The mainstays will be the further development of power plant concepts based on fossil (predominantly coal) and nuclear fuels; world-wide, also regenerative and CO 2 -free hydro-electric power will play a role. Rapid conversion of the available potential requires clear, long-term stable and reliable political framework conditions for the release of the necessary entrepreneurial forces. (orig.) [de

  19. Partner of nuclear power plants

    International Nuclear Information System (INIS)

    Gribi, M.; Lauer, F.; Pauli, W.; Ruzek, W.

    1992-01-01

    Sulzer, the Swiss technology group, is a supplier of components and systems for nuclear power plants. Important parts of Swiss nuclear power stations, such as containments, reactor pressure vessels, primary pipings, are made in Winterthur. Sulzer Thermtec AG and some divisions of Sulzer Innotec focus their activities on servicing and backfitting nuclear power plants. The European market enjoys priority. New types of valves or systems are developed as economic solutions meeting more stringent criteria imposed by public authorities or arising from operating conditions. (orig.) [de

  20. A model national emergency plan for radiological accidents; Plan modelo nacional de respuesta de emergencia para accidentes radiologicos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a result, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request.

  1. Radiological impact of emissions from reprocessing plants during normal operation

    International Nuclear Information System (INIS)

    Bonka, H.; Gruendler, D.; Hesel, D.; Muenster, M.; Schmidtlein, P.; Suender, B.

    1977-01-01

    When comparing the expected radiation exposure due to emissions from reprocessing plants with those from nuclear power plants it can be seen that the emissions from reprocessing plants contribute much more to the radiation exposure of the population than those from nuclear power plants. In the vicinity of reprocessing plants the highest contributions to the radiation exposure of the population are delivered by the following radionuclides: T, C 14 , Kr 85 , Sr 90 , Ru 106 , I 129 , Cs 134 , Cs 137 and Ce 144 as will as the Pu- and Cm-isotopes. Among these nuclides T, C 14 , Kr 85 und I 129 are globally distributed. While for T the contribution to the collective dose due to globally distributed T is small in comparison with the first pass exposure, the global contribution predominates for C 14 and Kr 85 . If an integration time of less than 10 5 years is considered, the contribution due to first pass exposure predominates for I 129 . When taking the radiation protection of the population into consideration, it seems sensible to retain 10% of T, 80 to 90% of C 14 , 90% of Kr 85 and 99,5% of I 129 in reprocessing plants and dispose of this material in a controlled manner. The fraction of the aerosols released should be about 10 -9 . Considering the global effects and the increasing number of nuclear power plants and reprocessing plants, an international agreement should be reached on these matters. (orig.) [de

  2. Modifications to nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

  3. Modifications to nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2007-01-01

    This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

  4. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

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

  5. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  6. Accumulation of radioactive cesium released from Fukushima Daiichi Nuclear Power Plant in terrestrial cyanobacteria Nostoc commune.

    Science.gov (United States)

    Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

    2013-01-01

    The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight (134)Cs and 607,000 Bq kg(-1) dry weight (137)Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil.

  7. Radiological emergency assessment of local decision support system

    International Nuclear Information System (INIS)

    Breznik, B.; Kusar, A.; Boznar, M.Z.; Mlakar, P.

    2003-01-01

    Local decision support system has been developed based on the needs of Krsko Nuclear Power Plant for quick dose projection and it is one of important features required for proposal of intervention before actual release may occur. Radiological emergency assessment in the case of nuclear accident is based on plant status analysis, radiation monitoring data and on prediction of release of radioactive sources to the environment. There are possibilities to use automatic features to predict release source term and manual options for selection of release parameters. Advanced environmental modelling is used for assessment of atmospheric dispersion of radioactive contamination in the environment. (author)

  8. Comparison of health and environmental effects of nuclear power plants and lignite-burning power plants

    International Nuclear Information System (INIS)

    Horacek, P.; Chytil, I.; Razga, J.

    1988-01-01

    The individual factors are discussed which characterize the impact of nuclear power plants and lignite-burning power plants on human health and on the environment. The study proceeds from the IAEA categorization of these impacts. In this light, attention is centred on the impact of the normal operation of power plants and on accidents. The former category is further divided into regional impacts such as the emission of chemical substances, the emission of radioactive substances, heat emissions and the sum of regional factors, and on global impacts such as emissions of carbon dioxide, emissions of long-lived radionuclides and the sum of global impacts. It is stated that research should pay more attention to the dangers of the effects of such a state of affairs when the infrastructure contaminated after a large-scale accident would be put out of operation, and the dangers of such a situation especially in small countries with great population densities. Such accidents represent the biggest danger of the use of nuclear power. The greatest danger of coal-burning power plants is their global impact on the atmosphere caused by the increasing concentration of carbon dioxide from burning fossil fuels. (Z.M.). 4 figs., 13 refs

  9. Control of renewable distributed power plants

    OpenAIRE

    Bullich Massagué, Eduard

    2015-01-01

    The main objective of this master thesis is to design a power plant controller for a photo- voltaic (PV) power plant. In a first stage, the current situation of the status of the electrical grid is analysed. The electrical network structure is moving from a conventional system (with centralized power generation, unidirectional power ows, easy control) to a smart grid system consisting on distributed generation, renewable energies, smart and complex control architecture and ...

  10. IAEA Perspectives on Radiological Characterisation

    International Nuclear Information System (INIS)

    O'Sullivan, Patrick; Ljubenov, Vladan

    2012-01-01

    Requirements for characterization of radiological and other hazards in nuclear facilities are reflected in the IAEA Safety Standards. WS-R-5, Safety Requirements for Decommissioning of Facilities using Radioactive Material, includes a requirement that 'During the preparation of the final decommissioning plan, the extent and type of radioactive material (irradiated and contaminated structures and components) at the facility shall be determined by means of a detailed characterization survey and on the basis of records collected during the operational period'. The subsidiary Safety Guide WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, further elaborates that 'A survey of radiological and non-radiological hazards provides an important input for the safety assessment and for implementing a safe approach during the work'. Although the characterisation requirements addressed in the Safety Standards relate primarily to the detailed survey activities undertaken following the shutdown of the facility, it is evident that radiological characterization is of relevance to all major phases of the lifetime of a nuclear facility, including: - the siting phase - baseline surveys are undertaken to determine background radiation levels; - the construction phase - construction materials are retained to support future calculations of radioactivity distributions; - the operational phase - surveys are done regularly, with additional surveys being required following incidents involving plant contamination; - the transition phase - detailed radiological surveys are required to support the development of the final decommissioning plan; and - the closure phase - a final survey of the site and any remaining structures will be needed to support an application for release of the site from regulatory control. In the case of facilities that are already shut down, the main purpose of radiological characterisation is to provide a reliable database of information on the

  11. Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

    International Nuclear Information System (INIS)

    Wood, R.S.

    1987-08-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document

  12. An Aerial Radiological Survey of the Beaver Valley Power Station and the Surrounding Areas

    International Nuclear Information System (INIS)

    Colton, D.P.

    1999-01-01

    An aerial radiological survey of the Beaver Valley Power Station was conducted during September 18 to 21, 1998, and encompassed a 53.1-square-kilometer area. The survey was conducted by the U. S. Department of Energy's Remote Sensing Laboratory, located in Las Vegas, Nevada, and maintained and operated by Bechtel Nevada. The purpose of the survey was to measure and map the general exposure-rate levels that existed within the survey area and to define the areas of man-made radionuclide activity. The inferred exposure rates were generally uniform and typical of the natural background radiation, which varied from less than 5 to 12 microroentgens per hour. Enhanced exposure rates, not attributable to natural background, and activity from man-made radionuclides were detected over the power station. The detected man-made radionuclide activity was due to the presence of cobalt-60, which is a nuclear activation product, and cesium-137, which is a long-lived fission product. The detected man-made radionuclides were generally consistent with those expected from routine plant operations. Areas outside of the power station boundaries were found to be free of any detectable man-made radionuclides. A series of ground-based, pressurized ionization chamber exposure-rate measurements were acquired at four locations within the survey boundaries. The results of these measurements were compared and found to be within 5 to 30 percent of the corresponding 1998 inferred aerial exposure-rate data

  13. Ardennes nuclear power plant

    International Nuclear Information System (INIS)

    1974-12-01

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

  14. A database structure for radiological optimization analyses of decommissioning operations

    International Nuclear Information System (INIS)

    Zeevaert, T.; Van de Walle, B.

    1995-09-01

    The structure of a database for decommissioning experiences is described. Radiological optimization is a major radiation protection principle in practices and interventions, involving radiological protection factors, economic costs, social factors. An important lack of knowledge with respect to these factors exists in the domain of the decommissioning of nuclear power plants, due to the low number of decommissioning operations already performed. Moreover, decommissioning takes place only once for a installation. Tasks, techniques, and procedures are in most cases rather specific, limiting the use of past experiences in the radiological optimization analyses of new decommissioning operations. Therefore, it is important that relevant data or information be acquired from decommissioning experiences. These data have to be stored in a database in a way they can be used efficiently in ALARA analyses of future decommissioning activities

  15. Probabilistic inhalation risk assessment due to radioactivity released from coal fired thermal power plants

    International Nuclear Information System (INIS)

    Tiwari, M.; Ajmal, P.Y.; Bhangare, R.C.; Sahu, S.K.; Pandit, G.G.

    2014-01-01

    This paper deals with assessment of radiological risk to the general public around in the neighborhood of a 1000 MWe coal-based thermal power plant. We have used Monte Carlo simulation for characterization of uncertainty in inhalation risk due to radionuclide escaping from the stack of thermal power plant. Monte Carlo simulation treats parameters as random variables bound to a given probabilistic distribution to evaluate the distribution of the resulting output. Risk assessment is the process that estimates the likelihood of occurrence of adverse effects to humans and ecological receptors as a result of exposure to hazardous chemical, radiation, and/or biological agents. Quantitative risk characterization involves evaluating exposure estimates against a benchmark of toxicity, such as a cancer slope factor. Risk is calculated by multiplying the carcinogenic slope factor (SF) of the radionuclide by the dose an individual receives. The collective effective doses to the population living in the neighborhood of coal-based thermal power plant were calculated using Gaussian plume dispersion model. Monte Carlo Analysis is the most widely used probabilistic method in risk assessment. The MCA technique treats any uncertain parameter as random variable that obeys a given probabilistic distribution. This technique is widely used for analyzing probabilistic uncertainty. In MCA computer simulation are used to combine multiple probability distributions associated with the dose and SF depicted in risk equation. Thus we get a probabilistic distribution for the risk

  16. Results of the benchmarking in radiological protection practices during fuel reloads in the nuclear power plants of Limerick (BWR) and Ginna (PWR) in the United States of North America; Resultados del benchmarking en practicas de proteccion radiologica durante recargas de combustible en las centrales nucleoelectricas de Limerick (BWR) y Ginna (PWR) en los Estados Unidos de Norteamerica

    Energy Technology Data Exchange (ETDEWEB)

    Lara H, M. A., E-mail: marco.lara@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2011-11-15

    The nuclear power plant of Laguna Verde, unique in our country, has been imposed several goals related with the continuous improvement of their acting; increase in the quantity of continuous days for operation cycle, improvement in the chemical indexes of the reactor coolant, improvement in the indexes of nuclear security, improvement in the indicators of industrial security, improvement in the standards of radiological protection, etc.; in this last item is precisely where is necessary to search creative solutions to be able to maintain the collective doses of the personnel so low as reasonably it is possible (ALARA) especially due to the last projects of extension of useful life of the nuclear power plant (zinc injection, noble metals and hydrogen) and of power increment of the nuclear power plant of Laguna Verde, same that represent in the short period an increment of collective dose and of exposition levels (until 200%) in very specific points of the primary systems of the reactor. (Author)

  17. Latina nuclear power plant

    International Nuclear Information System (INIS)

    1976-03-01

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

  18. Dynamic Frequency Response of Wind Power Plants

    DEFF Research Database (Denmark)

    Altin, Müfit

    according to their grid codes. In these scenarios particularly with high wind power penetration cases, conventional power plants (CPPs) such as old thermal power plants are planned to be replaced with wind power plants (WPPs). Consequently, the power system stability will be affected and the control...... to maintain sustainable and reliable operation of the power system for these targets, transmission system operators (TSOs) have revised the grid code requirements. Also, the TSOs are planning the future development of the power system with various wind penetration scenarios to integrate more wind power...... capability of WPPs would be investigated. The objective of this project is to analyze and identify the power system requirements for the synchronizing power support and inertial response control of WPPs in high wind power penetration scenarios. The dynamic frequency response of WPPs is realized...

  19. Power plant perspectives for sugarcane mills

    International Nuclear Information System (INIS)

    Bocci, E.; Di Carlo, A.; Marcelo, D.

    2009-01-01

    Biomass, integral to life, is one of the main energy sources that modern technologies could widely develop, overcoming inefficient and pollutant uses. The sugarcane bagasse is one of the more abundant biomass. Moreover, the fluctuating sugar and energy prices force the sugarcane companies to implement improved power plants. Thanks to a multiyear collaboration between University of Rome and University of Piura and Chiclayo, this paper investigates, starting from the real data of an old sugarcane plant, the energy efficiency of the plant. Furthermore, it explores possible improvements as higher temperature and pressure Rankine cycles and innovative configurations based on gasifier plus hot gas conditioning and gas turbine or molten carbonate fuel cells. Even if the process of sugar extraction from sugarcane and the relative Rankine cycles power plants are well documented in literature, this paper shows that innovative power plant configurations can increase the bagasse-based cogeneration potential. Sugarcane companies can become electricity producers, having convenience in the use of sugarcane leaves and trash (when it is feasible). The worldwide implementation of advanced power plants, answering to a market competition, will improve significantly the renewable electricity produced, reducing CO 2 emissions, and increasing economic and social benefits.

  20. Optimal control systems in hydro power plants

    International Nuclear Information System (INIS)

    Babunski, Darko L.

    2012-01-01

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

  1. ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.

    1991-01-01

    Implementation of the ALARA principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed through a variety of dose reduction techniques. Initiatives by the ICRP, NCRP, NRC, INPO, EPRI, and BNL ALARA Center have all contributed to a heightened interest and emphasis on dose reduction. The NCRP has formed Scientific Committee 46-9 which is developing a report on ALARA at Nuclear Power Plants. It is planned that this report will include material on historical aspects, management, valuation of dose reduction ($/person-Sv), quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report

  2. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    verification' are used differently in different countries. The way that these terms have been used in this Safety Guide is explained in Section 2. The term 'design' as used here includes the specifications for the safe operation and management of the plant. This Safety Guide identifies the key recommendations for carrying out the safety assessment and the independent verification. It provides detailed guidance in support of IAEA, Safety of Nuclear Power Plants: Design, Safety Standards Series No. NS-R-1 (2000), particularly in the area of safety analysis. However, this does not include all the technical details which are available and reference is made to other IAEA publications on specific design issues and safety analysis methods. Specific deterministic or probabilistic safety targets or radiological limits can vary in different countries and are the responsibility of the regulatory body. This Safety Guide provides some references to targets and limits established by international organizations. Operators, and sometimes designers, may also set their own safety targets which may be more stringent than those set by the regulator or may address different aspects of safety. In some countries operators are expected to do this as part of their 'ownership' of the entire safety case. This Safety Guide does not include specific recommendations for the safety assessment of those plant systems for which dedicated Safety Guides exist. Section 2 defines the terms 'safety assessment', 'safety analysis' and 'independent verification' and outlines their relationship. Section 3 gives the key recommendations for the safety assessment of the principal and plant design requirements. Section 4 gives the key recommendations for safety analysis. It describes the identification of postulated initiating events (PIEs), which are used throughout the safety assessment including the safety analysis, the deterministic transient analysis and severe accident analysis, and the probabilistic safety analysis

  3. Adaptive Reactive Power Control of PV Power Plants for Improved Power Transfer Capability under Ultra-Weak Grid Conditions

    DEFF Research Database (Denmark)

    Yang, Dongsheng; Wang, Xiongfei; Liu, Fangcheng

    2018-01-01

    with the unity power factor. Then, considering the reactive power compensation from PV inverters, the minimum SCR in respect to Power Factor (PF) is derived, and the optimized coordination of the active and reactive power is exploited. It is revealed that the power transfer capability of PV power plant under...... of a 200 MW PV power plant demonstrate that the proposed method can ensure the rated power transfer of PV power plant with the SCR of 1.25, provided that the PV inverters are operated with the minimal PF=0.9.......This paper analyzes the power transfer limitation of the PV power plant under the ultra-weak grid condition, i.e., when the Short-Circuit Ratio (SCR) is close to 1. It explicitly identifies that a minimum SCR of 2 is required for the PV power plant to deliver the rated active power when operating...

  4. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-12-01

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

  5. Safety Assessment - Swedish Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kjellstroem, B. [Luleaa Univ. of Technology (Sweden)

    1996-12-31

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs.

  6. Safety Assessment - Swedish Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kjellstroem, B.

    1996-01-01

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs

  7. Nuclear power plants: 2004 atw compact statistics

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    In late 2004, nuclear power plants were available for power supply or were under construction in 32 countries worldwide. A total of 441 nuclear power plants, i.e. two plants more than in late 2003, were in operation with an aggregate gross power of approx. 386 GWe and an aggregate net power, respectively, of 362 GWe, in 31 countries. The available capacity of nuclear power plants increased by approx. 5 GWe as a result of the additions by the six units newly commissioned: Hamaoka 5 (Japan), Ulchin 6 (Korea), Kalinin 3 (Russia), Khmelnitski 2 (Ukraine), Qinshan II-2 (People's Republic of China), and Rowno 4 (Ukraine). In addition, unit 3 of the Bruce A nuclear power plant in Canada with a power of 825 MWe was restarted after an outage of many years. Contrary to earlier plans, a recommissioning program was initiated for the Bruce A-1 and A-2 units, which are also down at present. Five plants were decommissioned for good in 2004; Chapelcross 1 to 4 with 50 MWe each in the United Kingdom, and Ignalina 1 with 1 300 MWe in Lithuania. 22 nuclear generating units with an aggregate gross power of 19 GWe in nine countries were under construction in late 2004. In India, construction work was started on a new project, the 500 MWe PFBR prototype fast breeder reactor. In France, the EDF utility announced its intention to build an EPR on the Flamanville site beginning in 2007. (orig.)

  8. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Nakayama, Ryoichi; Kimura, Motohiko; Abe, Akira

    1993-01-01

    A continuing need exists for automatic or remote-controlled machines or robots which can perform inspection and maintenance tasks in nuclear power plants. Toshiba has developed several types of monofunctional and multi- functional robots for such purposes over the past 20 years, some of which have already been used in actual plants. This paper describes new multifunctional robots for inspection and maintenance. An inspection robot has been applied in an actual plant for two years for performance testing. Maintenance robots for grinding tasks have also been developed, which can be easily teleoperated by the operator using automatic control. These new robots are expected to be applied to actual inspection and maintenance work in nuclear power plants. (author)

  9. Seismic reevaluation of existing nuclear power plants

    International Nuclear Information System (INIS)

    Hennart, J.C.

    1978-01-01

    The codes and regulations governing Nuclear Power Plant seismic analysis are continuously becoming more stringent. In addition, design ground accelerations of existing plants must sometimes be increased as a result of discovery of faulting zones or recording of recent earthquakes near the plant location after plant design. These new factors can result in augmented seismic design criteria. Seismic reanalysius of the existing Nuclear Power Plant structures and equipments is necessary to prevent the consequences of newly postulated accidents that could cause undue risk to the health or safety of the public. This paper reviews the developments of seismic analysis as applied to Nuclear Power Plants and the methods used by Westinghouse to requalify existing plants to the most recent safety requirements. (author)

  10. Radiological considerations in the design of Reprocessing Uranium Plant (RUP) of Fast Reactor Fuel Cycle Facility (FRFCF), Kalpakkam

    International Nuclear Information System (INIS)

    Chandrasekaran, S.; Rajagopal, V.; Jose, M.T.; Venkatraman, B.

    2012-01-01

    A Fast Reactor Fuel Cycle Facility (FRFCF) being planned at Indira Gandhi Centre for Atomic Research, Kalpakkam is an integrated facility with head end and back end of fuel cycle plants co-located in a single place, to meet the refuelling needs of the prototype fast breeder reactor (PFBR). Reprocessed uranium oxide plant (RUP) is one such plant in FRFCF to built to meet annual requirements of UO 2 for fabrication of fuel sub-assemblies (FSAs) and radial blanket sub-assemblies (RSAs) for PFBR. RUP receives reprocessed uranium oxide powder (U 3 O 8 ) from fast reactor fuel reprocessing plant (FRP) of FRFCF. Unlike natural uranium oxide plant, RUP has to handle reprocessed uranium oxide which is likely to have residual fission products activity in addition to traces of plutonium. As the fuel used for PFBR is recycled within these plants, formation of higher actinides in the case of plutonium and formation of higher levels of 232 U in the uranium product would be a radiological problem to be reckoned with. The paper discussed the impact of handling of multi-recycled reprocessed uranium in RUP and the radiological considerations

  11. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

    1984-01-01

    Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics. (author)

  12. Robotics for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

    1984-10-01

    Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics.

  13. Radiological characterisation - Know your objective

    International Nuclear Information System (INIS)

    Lindow, Veronica; Moeller, Jennifer

    2012-01-01

    When developing a programme for mapping the radiological characteristics of a facility to be decommissioned it is important to take into account the objectives of the programme. Will the results be used to plan for radiological control and selection of appropriate decontamination and dismantling techniques? Will the radiological inventory be used for dimensioning of future waste repositories? These are two examples of the applications for such studies, which could require that a radiological characterisation programme be adapted to provide the data appropriate to the intended use. The level of detail and scope needed for a radiological characterisation will also vary depending on how the data will be used. An application to free-release a facility requires a comprehensive survey and well documented analysis in order to ensure that no radioactive contamination above prescribed levels is present. A bounding calculation to determine the maximum anticipated volumes and activity of radioactive waste requires a different approach. During the past few years, older decommissioning studies for the Swedish nuclear power plants have been updated (or are in the process of being updated). The decommissioning study's main purpose is to estimate the cost for decommissioning. The cost estimation is based on material and activity inventories, which in turn is based on previous and, in some cases, updated radiological characterisations of the facilities. The radiological inventory is an important part of the study as it affects the cost of decommissioning but also the uncertainties and accuracy of the cost estimation. The presentation will discuss the challenges in specifying a radiological characterisation programme with multiple objectives, together with insights on how data delivered can be applied to yield results suitable for the intended purpose, without introducing excessive conservatism. The intent of the presentation is to define issues that can be of use in various aspects

  14. Geothermal Power Generation Plant

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-12-01

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

  15. Transportable nuclear power plant TEC-M with two reactor plants of improved safety

    International Nuclear Information System (INIS)

    Ogloblin, B.G.; Sazonov, A.G.; Svishchev, A.M.; Gromov, B.F.; Zelensky, V.N.; Komkova, O.I.; Sidorov, V.I.; Tolstopyatov, V.P.; Toshinsky, G.I.

    1993-01-01

    Liquid metals are the best to meet the requirements of inherently safety nuclear power plants among the coolants used. A great experience has been gained in lead coolant power plant development and operation as applied to transportable power set-ups. Low chemical activity of this coolant with respect to air-water interaction is a determining factor for this coolant. The transportable nuclear power plant is described. It is intended to generate electric power for populated areas placed a long distance from the main electric power supply sources where it is difficult or not economical to deliver the conventional types of fuel. There are several remote areas in Siberia, Kamchatka in need of this type of power plant

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

    Directory of Open Access Journals (Sweden)

    Gerardo Guerra

    2017-11-01

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

  17. Monitoring support system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashikawa, Yuichi; Kubota, Rhuji; Tanaka, Keiji; Takano, Yoshiyuki

    1996-01-01

    The nuclear power plants in Japan reach to 49 plants and supply 41.19 million kW in their installed capacities, which is equal to about 31% of total electric power generation and has occupied an important situation as a stable energy supplying source. As an aim to keeping safe operation and working rate of the power plants, various monitoring support systems using computer technology, optical information technology and robot technology each advanced rapidly in recent year have been developed to apply to the actual plants for a plant state monitoring system of operators in normal operation. Furthermore, introduction of the emergent support system supposed on accidental formation of abnormal state of the power plants is also investigated. In this paper, as a monitoring system in the recent nuclear power plants, design of control panel of recent central control room, introduction to its actual plant and monitoring support system in development were described in viewpoints of improvement of human interface, upgrade of sensor and signal processing techniques, and promotion of information service technique. And, trend of research and development of portable miniature detector and emergent monitoring support system are also introduced in a viewpoint of labor saving and upgrade of the operating field. (G.K.)

  18. Plant life management study of Japanese nuclear power plants

    International Nuclear Information System (INIS)

    Fukuda, Toshihiko

    1999-01-01

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

  19. The future of integrated coal gasification combined cycle power plants

    International Nuclear Information System (INIS)

    Mueller, R.; Termuehlen, H.

    1991-01-01

    This paper examines the future of integrated coal gasification combined cycle (IGCC) power plants as affected by various technical, economical and environmental trends in power generation. The topics of the paper include a description of natural gas-fired combined cycle power plants, IGCC plants, coal gasifier concepts, integration of gasifiers into combined cycle power plants, efficiency, environmental impacts, co-products of IGCC power plants, economics of IGCC power plants, and a review of IGCC power plant projects

  20. Toxic releases from power plants

    International Nuclear Information System (INIS)

    Rubin, E.S.

    1999-01-01

    Beginning in 1998, electric power plants burning coal or oil must estimate and report their annual releases of toxic chemicals listed in the Toxics Release Inventory (TRI) published by the US Environmental Protection Agency (EPA). This paper identifies the toxic chemicals of greatest significance for the electric utility sector and develops quantitative estimates of the toxic releases reportable to the TRI for a representative coal-fired power plant. Key factors affecting the magnitude and types of toxic releases for individual power plants also are discussed. A national projection suggests that the magnitude of electric utility industry releases will surpass those of the manufacturing industries which current report to the TRI. Risk communication activities at the community level will be essential to interpret and provide context for the new TRI results