WorldWideScience

Sample records for atomic power plant

  1. Offshore atomic power plants

    International Nuclear Information System (INIS)

    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.)

  2. Human factors in atomic power plant

    International Nuclear Information System (INIS)

    To ensure safety should have priority over all other things in atomic power plants. In Chernobyl accident, however, various human factors including the systems for bulb check after inspection and communication, troubles in the interface between hardwares such as warning speakers and instruments, and their operators, those in education and training for operators and those in the general management of the plant have been pointed out. Therefore, the principles and the practical measures from the aspect of human factors in atomic power plants were discussed here. The word, ''human factor'' was given a definition in terms of the direct cause and the intellectual system. An explanatory model for human factors, model SHEL constructed by The Tokyo Electric Power Co., Ltd., Inc. was presented; the four letter mean software(S), hardware(H), environment(E) and liveware(L). In the plants of the company, systemic measures for human error factors are taken now in all steps not only for design, operation and repairing but also the step for safety culture. Further, the level required for the safety against atomic power is higher in the company than those in other fields. Thus, the central principle in atomic power plants is changing from the previous views that technology is paid greater importance to a view regarding human as most importance. (M.N.)

  3. Plant power supply device in an atomic power plant

    International Nuclear Information System (INIS)

    Object: To avoid tripping of a 6.9 kV class bus line and to decrease a large electric current momentarily flown into a start transformer, in despite of the fact that the bus line is not changed over resulted from actuation of a generator lock-out relay. Structure: An atomic power plant comprising a bus line for a two-system plant power supply and a start transformer receiving power from an exterior system, characterized by the provision of a breaker for effecting the change-over of only one system bus line simultaneously with the reactor scrum and a breaker for effecting the change-over of the other bus line before a generator is tripped as a result of actuation of a generator lock-out relay in a predetermined period of time after the reactor scrum, to thereby reduce the momentary large current to the start transformer. (Kamimura, M.)

  4. Are atomic power plants saver than nuclear power plants

    International Nuclear Information System (INIS)

    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.)

  5. Geologic survey for atomic power-plant, (2)

    International Nuclear Information System (INIS)

    The author has presented a general treatise on the above title previously, in which the geology and aseismatic design criteria for atomic power-plants in Japan were considerably precisely described. In the present paper, such criteria and surveying prescription now adopted in U.S.A. are first introduced, in which special weight is laid on the vibrative characteristics and structural geologic conditions of plant ground which have large influence on the effects of earthquakes, fault-movement and some accidental shocks that may be inflicted on power stations. Next, as a home example of the geologic survey for atomic power-plants, that performed for the Genkai Power plant in Kyushu now its construction is almost completed, is introduced. Besides general geologic survey of ground and the examination of various physico-mechanical characteristics of site rocks, special tests were carried out for the estimation of the nature and degree of ground vibration at the time of natural and accidental shocks. One of them thus performed is the observation of elastic waves (P and S) caused by blasting in surveying tunnels opened near the reactor site. The data of the vibrative characteristics of ground obtained from these tests are also indespensable for the regulation of blasting method in the excavating work of basal ground for the construction of additional reactors in the vicinity of operating atomic power plants. (Shibata, I.)

  6. Seismic considerations in the design of atomic power plants

    International Nuclear Information System (INIS)

    A seismic design is one of the most important factors for the safety of nuclear power plants constructed in seismic areas. The various considerations in the design of atomic power plant structures and components to achieve high degree (near absolute) of safety during future probable earthquakes is described as follows: (a) determination of design earthquake parameters for SSE and OBE (b) fixing time history accelerograms and acceleration response spectra (c) mathematical modelling of the reactor building considering soil-structure interaction (d) deciding allowable stresses, damping factors and serviceability limits like drift, displacements and crack widths (e) tests for determining stiffness and damping characteristics of components in-situ before commissioning of plant. The main questions that arise under various items requiring further research investigations or development work are pointed out for discussion. (author)

  7. Plant life management experience at Tarapur Atomic Power Station

    International Nuclear Information System (INIS)

    Tarapur Atomic Power Station, the longest serving Nuclear Power Plant in the Asian continent has completed 36 years of successful operation and generated more than 70 Billion units of electric power. Built in late sixties, with the state-of-the-art safety features prevailing then, TAPS through the process of evolution has become much more safer plant due to efforts of upgradation, renovation and refurbishment prompted by the station's operating experience, feed back from overseas reactors, lessons learnt from nuclear incidents, accidents and fresh review of design basis and safety analysis of the plant. All components of a Nuclear power plant experience some degradation with time. The Reactor Pressure Vessels (RPV) designed for 40 effective full power years (EFPY) of operation have operated for less than 21 EFPY and the material condition is assessed to be fit for several more years of service. The condition of the containment and main plant buildings was assessed to be satisfactory. The Life Management Programme involved identification of key systems, structures and components (SSCs) that may experience degradation due to ageing, and take corrective measures through maintenance, repair and / or replacement. The identified components were classified as major critical components, important systems and other critical components. For each component mode of degradation was identified, ageing assessment was done and action plan was finalized. Replacement of some important equipment like 3X50% capacity Emergency Diesel Generators (EDG) with 3 X 100% capacity EDG, Salt Service Water (SSW) pumps, Control rod drive (CRD) pumps, Emergency Condenser tube bundles, Station battery has been done on the basis of condition monitoring and to obviate common cause failure and enhance the system reliability. Samples of Safety related cables were subjected to residual life assessment (RLA) and replacement action firmed up on the basis of the RLA findings. Condition survey of Main plant

  8. Plant life management experience at Tarapur Atomic Power Station

    International Nuclear Information System (INIS)

    The twin BWR reactors of Tarapur Atomic Power Station (TAPS) are in their 38th year of successful operation and have generated more than 71 billion units of electric power. The plant has seen continuous evolution based on operating experience, feedback from overseas reactors, lessons learnt from nuclear incidents, accidents and fresh review of design basis and safety analysis of the plant due to efforts of upgradation, renovation and refurbishment. The Plant Life Management involved establishing an Ageing Management Programme (AMP). The AMP involved identification of key systems, structures and components (SSCs) that may experience degradation due to ageing, and take corrective measures through maintenance, repair and/or replacement. The identified components were identified as major critical components, important systems and other critical components. The components were further classified as not replaceable, difficult to replace and replaceable on routine basis. The various degradation mechanisms (Stress Corrosion Cracking (SCC), Intra Granular Stress Corrosion Cracking (IGSCC), Trans Granular Stress Corrosion Cracking (TGSCC), Erosion Corrosion (EC), Flow Accelerated Corrosion (FAC), Temperature, Pressure, Humidity, Radiation, etc.,) were identified for critical components, their method of detection, methodologies followed for In-Service inspection and developmental activities to assess the integrity of nuclear reactor vessels, piping and components for continued service. For each component mode of degradation was identified, ageing assessment was done and action plan was finalized. A comprehensive examination was carried out on Structures, Systems and Components (SSCs) as part of plant ageing management programme

  9. Plant water supplying device for atomic power plant

    International Nuclear Information System (INIS)

    Purpose: To smoothly and accurately supply plant feedwater. Constitution: When plant feedwater in a feedwater tank is discharged to a plant by a feedwater pump, the reduction in the discharge pressure due to the decrease in the lift of the feedwater in the tank is corrected by increasing the rotational speed of the pump, and the pressure of the feedwater is always kept constantly. According to this device, the flow rate of the feedwater can be widely controlled by one feedwater pump, and the number of pumps can be reduced. (Kamimura, K.)

  10. On manual stop of No.1 plant in Tsuruga Power Station, Japan Atomic Power Co

    International Nuclear Information System (INIS)

    No. 1 plant in Tsuruga Power Station, Japan Atomic Power Co., is a BWR plant with rated output of 357 MWe, and while it was operated at the rated output, the functional test on high pressure water injection system was carried out on January 5, 1990. After 10:00 a.m., the flow rate of the high pressure water injection system pump decreased suddenly, and the diesel engine driving the pump stopped automatically. As the result of checkup, damage was observed in the speed increasing gear connecting the diesel engine and the pump. It is considered that long time is required for the restoration, therefore, the lowering of power output was begun at 0:00 a.m., January 10, and the reactor was manually shut down at 8:00 a.m.. (K.I.)

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

    International Nuclear Information System (INIS)

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

  12. Trends of personal dosimetry at atomic power plants

    International Nuclear Information System (INIS)

    The individual dosimetry at the atomic power station is sorted for monthly dosimetry, daily dosimetry and special job dosimetry in high dose circumstance. Film badge (passive dosimeter) can measure gamma dose, beta dose and neutron dose respectively lower than about 0.1 mSv. While workers are in the radiation controlled area, they have to wear the dosimeters and the individual dose is accumulated for every one month. Recently the Silicon semiconductors detecting beta ray and neutron have been developed. With microcircuit technology and these new sensors, new multiple function dosimeter of the card size had been put to practical use. The result of dose measurement obtained by the electronic dosimeter is consistent well with the measurement of usual film badge and new dosimeter can determine the dose as low as 0.01 mSv. The result is stored in the non-volatile memory in the electronic personal dosimeter and held for more than one year without the power supply. The function to read data directly from the memory improves the reliability of the data protection. The realization of the unified radiation control system that uses the electronic personal dosimeter for monthly dosimetry is expected. (J.P.N.)

  13. Atomic Information Technology Safety and Economy of Nuclear Power Plants

    CERN Document Server

    Woo, Taeho

    2012-01-01

    Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

  14. Atomic Power Safety

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John F

    1964-01-01

    This booklet is condensed from a larger publication, -Background Information on Atomic Power Safety-, published in January 1964, by the .Atomic Industrial Forum. That publication and this abridgment were produced in recognition of the emergence of commercial atomic power as an important factor in our national economy, and of the resulting need for readily available information in nontechnical form on the characteristics of nuclear power plants and on the various measures taken during their design, construction, and operation for public safety.

  15. The truth about atomic power plants. 2. ed.

    International Nuclear Information System (INIS)

    The book discusses - the risk of nuclear power, - the dangers of population exposure, - hushed-up or belittled accidents and catastrophes, - the increasing radioactive pollution of our environment, - the hazard of nuclear cooling water to our rivers - blue algare toxins in our rivers. The strongest of all known poisons, - dangers to our drinking water, - necessary measures to protect the population. (orig./HP)

  16. Genetic effects of prolonged combined irradiation of laboratory animals in Chernobyl Atomic Power Plant alienation zone

    International Nuclear Information System (INIS)

    Prolonged combined (external and internal) irradiation of mice in the r zone of the Chernobyl Atomic Power Plant caused hereditary disturbances physiological defects in the posterity irrespective of the fact if one or both parents were irradiated. The most favourable indices were observed in F2 posterity of the both exposed parents

  17. Fuel-element inspection stand in the cooling pond of an atomic power plant

    International Nuclear Information System (INIS)

    A fuel-element inspection stand has been built in the cooling pool of the second power unit at the Ignalina Atomic Power Plant for the purpose of monitoring fuel elements unloaded from the reactor and for performing research involving the acquisition and analysis of statistically significant information concerning the reliability and efficiency of fuel elements and fuel bundles. The uses and specifications of the fuel-element inspection stand are given in this paper. 1 ref., 4 figs

  18. Suitability of using atomic energy at existing thermal electrical power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nosach, V.G.; Rogovoi, V.T.

    1976-01-01

    A thermal concept is described for the simultaneous use of atomic and organic fuels at existing electrical thermal power plants. Equations are presented for the mass and heat balances, from which a preliminary calculation of this thermal concept was carried out. The results indicate that it is efficient to use a nuclear reactor at thermal electrical power plants, as a result of which up to 50% of the total heat is produced by nuclear fuel, while the consumption of organic is decreased by almost a factor of two in this case. 4 figures, 3 references.

  19. Integrated plant safety assessment: systematic evaluation program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company. Docket No. 50-213

    International Nuclear Information System (INIS)

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  20. Floating atomic central heating-and-power plant converted from a strategic submarine

    International Nuclear Information System (INIS)

    In accordance with open-quotes The Treaty on the Reduction of Strategic Offensive Armsclose quotes signed in July 1991, the operations envisages by open-quotes The Procedures for elimination of SSBN's Launchersclose quotes should be accomplished at submarines of the second generation both by eliminating missile compartments together with launchers and by removal of launchers only from missile compartments. THe number of such ships could reach 30 units as has been forecasted for the year of 1998 inclusive. With regard to the fact that the remaining operation life of the main power plant equipment of a nuclear submarine decommissioned in accordance with the Treaty is about 50 per cent, potentially there is a possibility to convert them into floating atomic central heating-and-power plants. The latter variant envisaged in the open-quotes Procedures...close quotes is preferable for developing a floating plant based on ships decommissioned from the Navy, since it permits to remove launchers without cutting and subsequent connection of main cables, pipelines and systems which provide the control of the main power plant, nuclear safety, radiological safety, damage control and fire safety of the floating plant. A submarine could be delivered for refitting into a floating plant only after accomplishing the works envisaged by the open-quotes Procedures...close quotes

  1. The role of the International Atomic Energy Agency safety missions in upgrading plant safety at Krsko nuclear power plant

    International Nuclear Information System (INIS)

    The role of the International Atomic Energy Agency (IAEA) safety missions in upgrading plant safety at Krsko NPP is defined. Krsko NPP is a two loop PWR plant designed by Westinghouse. The safety missions, following the invitation of the Yugoslavian Government, visited the plant on numerous occasions from the early construction phase to full power operation. The purpose of inviting the missions was to provide a second independent international viewpoint on various subjects related to safety features of plant design, equipment characteristics, utility organization during contruction and operation, quality control and quality assurance programmes and plant commissioning. The main activities of the IAEA missions during plant construction were related to the analysis of the preliminary and final safety analysis reports, especially where specific site conditions deviate from the standard United States Regulatory Guides (for example site meteorology and related environmental dose calculations) or where new design features have been introduced (such as 16x16 fuel design or emergency core cooling systems for two loop plants). Special consideration has been given to plant safety systems upgrading, particularly since the Three Mile Island accident. Mission advice on this subject was very valuable because it has provided the utility and licensing body with independent engineering judgements on the merit of particular hardware changes. In addition, the missions spent considerable time in analysing the role, functions and training of regulatory body personnel, the functions of utility organizations, especially in the areas related to safety (function of the quality assurance department and future organization for plant operation). Following the start of plant commercial operation the IAEA was invited to send the Operational Safety Review Team and the Assessment of Safety Significant Events Team. The paper describes the outcome of these missions. Finally, some general comments

  2. Atomic power's powered atomiser

    International Nuclear Information System (INIS)

    As an extension of its traditional activities the United Kingdom Atomic Energy Authority (UKAEA) has developed a range of products and services. So far one of its most successful ventures has been the licensing of power fluidics technology in the hvac (heating, ventilation and air conditioning) market. Power Fluidics is the control of liquid or gas flows without the use of any moving parts. The UKAEA has developed the vortex amplifier, a control device, which has many potential applications, in which the process flow is throttled and turned down as the control flow is increased. The bistable flow diverter in which a coanda effect diverts the flow down one of two outlets has possible uses in the water industry as well. Another development is a device for controlling fluid droplet size in which a bistable converter has a feedback loop which ensures continuous switching of the flow. By opposing the nozzle outlets, the alternating flows collide in a controlled manner and droplet size can be controlled. (U.K.)

  3. 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…

  4. Prestressing works of PCCV for Tsuruga No.2 plant of Japan Atomic Power Co

    International Nuclear Information System (INIS)

    Recently, the structure adopting prestressed concrete techniques has been completed for the first time in a Japanese nuclear facility, and it is the prestressed concrete containment vessel (PCCV) for Tsuruga No.2 plant of Japan Atomic Power Co. In this PCCV, as the prestressing system, the large stretching capacity tendons (1035 t/tendon) by BBRV construction method were adopted, in addition, those were used by unbonded technique without adhering to the concrete body. Besides, PCCVs are particularly important structures in view of the safety among nuclear facilities, therefore they must satisfy many strict standards. In this report, how the prestressed concrete techniques, which have been established as the consistent system including the design of tendon arrangement, the manufacture of system parts, rust prevention treatment, the working equipment, stretching control, the quality control and quality assurance, was materialized in this PCCV is described. The BBRV construction method has been generally known by fixing the ends of PC wires with cold worked buttonheads. PS system parts, the assurance test of PS system, the manufacture of tendons, and the works of inserting, stretching and greasing are described. (Kako, I.)

  5. ASCERTAINMENT OF ELECTRIC-SUPPLY SCHEMES RELIABILITY FOR THE ATOMIC POWER PLANT AUXILIARIES

    Directory of Open Access Journals (Sweden)

    A. L. Starzhinskij

    2015-01-01

    Full Text Available The paper completes ascertainment of electrical-supply scheme reliability for the auxiliaries of a nuclear power plant. Thereat the author considers the system behavior during the block normal operation, carrying out current maintenance, and capital repairs in combination with initiating events. The initiating events for reactors include complete blackout, i.e. the loss of outside power supply (normal and reserve; emergency switching one of the working turbogenerators; momentary dumping the normal rating to the level of auxiliaries with seating the cutout valve of one turbo-generator. The combination of any initiating event with the repairing mode in case of one of the system elements failure should not lead to blackout occurrence of more than one system of the reliable power supply. This requirement rests content with the help of the reliable power supply system self-dependence (electrical and functional and the emergency power-supply operational autonomy (diesel generator and accumulator batteries.The reliability indicators of the power supply system for the nuclear power plant auxiliaries are the conditional probabilities of conjoined blackout of one, two, and three sections of the reliable power supply conditional upon an initiating event emerging and the blackout of one, two, and three reliable power-supply sections under the normal operational mode. Furthermore, they also are the blackout periodicity of one and conjointly two, three, and four sections of normal operation under the block normal operational mode. It is established that the blackout of one bus section of normal operation and one section of reliable power-supply system of the auxiliaries that does not lead to complete blackout of the plant auxiliaries may occur once in three years. The probability of simultaneous power failure of two or three normal-operation sections and of two reliable power-supply sections during the power plant service life is unlikely.

  6. Environmental radionuclide concentrations in the vicinity of the Calvert Cliffs Nuclear Power Plant and the Peach Bottom Atomic Power Station: 1996--1997. Final report

    International Nuclear Information System (INIS)

    The Maryland Power Plant Research Program monitors concentrations of natural, weapons, and power plant produced radionuclides in environmental samples collected from the Chesapeake Bay in the vicinity of the Calvert Cliffs Nuclear Power Plant (CCNPP) and from the Susquehanna River-Chesapeake Bay system in the vicinity of Peach Bottom Atomic Power Station (PBAPS). The purpose of this monitoring is to determine the fate, transport, and potential effects of power plant-produced radionuclides. This report contains a description of monitoring activities and data collected during the 1996 and 1997 calendar years. Radionuclide concentrations in shellfish, finfish, aquatic vegetation, and sediment were measured using high-resolution gamma spectrometry. Radionuclides in environmental samples originated from natural sources, historic atmospheric weapons testing, and normal operations of CCNPP and PBAPS

  7. Effort to grapple with improvement of security and reliability of nuclear power plant. Actions of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Following the Great Tohoku Earthquake in 2011, Tokai No.2 reactor was shut down automatically. Three of emergency diesel generators worked automatically at loss-of-offsite-power and began to work the cooling system of reactor. The reactor could be kept stable and safe in cold state by management of power from the gas turbine electric generator and power source car. Actions of Japan Atomic Power Company (JAPC) for cold shutdown and Tsunami were stated. Inspection results after the earthquake and testimony of staff was described. Countermeasure of improvement of safety of nuclear power station is explained by ensuring of power source and water supply, crisis management system, countermeasure of accident, ensuring, and training of workers, and action for better understanding of reliance. (S.Y.)

  8. Integrated Plant Safety Assessment: Systematic Evaluation Program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Docket No. 50-213. Final report

    International Nuclear Information System (INIS)

    The Systematic Evaluation Progam was initiated in February 1977 by the US Nuclear Regulatory Commission review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with curent licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  9. International Co-Operation on the Safety of Nuclear Power Plants within the Framework of the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    The Director General has received from three Member States the following communications regarding international co-operation on the safety of nuclear power plants within the framework of the International Atomic Energy Agency: (i) Letter dated 17 May 1979 from the Federal Minister for Research and Development of the Federal Republic of Germany, together with the explanation of the proposal made by the Government of the Federal Republic of Germany; (ii) Letter dated 21 May 1979 from the Resident Representative of Brazil to the Agency; (iii) Letter dated 31 May 1979 from the Minister for Foreign Affairs of Sweden.

  10. Assessment of effects of structural response on plant risk. Preliminary results for Peach Bottom Atomic Power Station

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission has been sponsoring tests at Los Alamos National Laboratory on the dynamic response of Seismic Category I reinforced concrete shear wall structures. As test results accumulated, it became clear that there was a significant difference between as-calculated and measured shear wall stiffnesses and frequencies, and that these differences existed both in static and dynamic tests. For very low level tests, measured frequencies were found to range between 50% and 80% of the computed values. During simulated earthquake tests, measured frequencies were found to further decrease as the earthquake level increased. The observed differences between calculated and measured stiffnesses and frequencies represents a potentially important issue relative to the seismic design and safety of nuclear power plants. Thus, this frequency difference issue has potentially important implications with respect to the safety of power plants during seismic events. In order to assess the importance of this frequency difference issue the US Nuclear Regulatory Commission has funded Sandia National Laboratories to re-evaluate several existing seismic PRAs by modeling and incorporating the effects of the frequency reductions. This report presents the results for the initial re-evaluation of the seismic risk at the Peach Bottom Atomic Power Station

  11. Seismic analysis of two heavy water upgrading towers for 500 MWe Tarapur Atomic Power Plant-3 and 4

    International Nuclear Information System (INIS)

    The report deals with the analysis carried out for the evaluation of earthquake induced stresses and deflections in two 1500 mm diameter heavy water upgrading towers for Tarapur Atomic Power Plant-3 and -4. The analysis of upgrading towers has been carried out for two mutually perpendicular horizontal excitations and one vertical excitation applied simultaneously. The upgrading towers have been analysed using beam model taking into account soil-structure interaction. Response spectrum analysis has been carried out using envelope spectra for 500 MWe sites. The seismic analysis has been carried out for the towers with supporting structure along with concrete pedestals and raft foundation. The towers have been checked for their stability due to compressive stresses to avoid buckling so that safety of the nearby structures is not damaged even in the event of SSE (Safe Shutdown Earthquake) loading. (author). 16 refs., 11 figs., 18 tabs

  12. Seismic analysis of two 1050 mm diameter heavy water upgrading towers for 235 MWe Kaiga Atomic Power Plant Site

    International Nuclear Information System (INIS)

    This report deals with the analysis carried out for the evaluation of earthquake induced stresses and deflections in two 1050 mm diameter heavy water upgrading towers for Kaiga Atomic Power Plant Site. The analysis of upgrading tower has been carried out for two mutually perpendicular horizontal excitations and one vertical excitation applied simultaneously. The upgrading towers have been analysed using beam model taking into account soil-structure interaction. Response spectrum analysis has been carried out using site spectra for 235 MWe Kaiga reactor site. The seismic analysis has been performed for both the towers with supporting structure along with concrete pedestals and raft foundation. The towers have been checked for its stability due to compressive stresses to avoid buckling so that the nearby safety related structures are not geopardised in the event of safe shutdown earthquake (SSE) loading. (author). 14 refs., 12 figs., 18 tabs

  13. Seismic analysis of two 1050 mm diameter heavy water upgrading towers for 235 MWe Kakrapar Atomic Power Plant Site

    International Nuclear Information System (INIS)

    This report deals with the analysis carried out for the evaluation of earthquake induced stresses and deflections in two 1050 mm diameter heavy water upgrading towers for Kakrapar Atomic Power Plant Site. The analysis of upgrading tower has been carried out for two mutually perpendicular horizontal excitations and the vertical excitation. The upgrading towers have been analysed using beam model taking into account soil-structure interaction. response spectrum analysis has been carried out using site spectra for 235 MWe KAPP site. The seismic analysis has been carried out for both the towers with supporting structure along with concrete pedestals and raft foundation. The towers have been checked for their stability due to compressive stresses to avoid buckling so that the nearby safety related structures are not damaged in the event of SSE loading. (author). 13 refs., 11 figs., 14 tabs

  14. Results of second regular inspection of No.2 plant in Tsuruga Power Station, Japan Atomic Power Co

    International Nuclear Information System (INIS)

    The second regular inspection of No.2 plant in Tsuruga Power Station was carried out from April 11 to July 26, 1989. The parallel operation was resumed on July 1, 1989, 82 days after the parallel off. The facilities which were the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency electric power generation system. On the facilities which were the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, as the result, the return flow rate from No.1 seal of a primary coolant pump increased, and the reactor automatically stopped as a motor-driven feed pump tripped, but other abnormality was not observed. The works related to this regular inspection were accomplished within the range of the limit of radiation dose equivalent based on the relevant laws. Particular main reconstruction work was not carried out during the period of this regular inspection. (K.I.)

  15. Results of fourteenth regular inspection of No.1 plant in Tsuruga Power Station, Japan Atomic Power Co

    International Nuclear Information System (INIS)

    The fourteenth regular inspection of No.1 plant in the Tsuruga Power Station was carried out from September 16, 1983, to January 20, 1984. The objects of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment facilities and emergency standby power generation system. The inspection of appearance, disassembled components, leak, function, performance and so on was carried out on these objects, but abnormality was not found. The works related to this regular inspection were carried out within the range of the allowable dose based on the laws. The main reconstruction works carried out during this inspection were the additional installation of an ionization chamber detector to an exhaust funnel monitor, the installation of two radiation monitors each on the dry well and suppression chamber, the reconstruction of the ventilation system for the turbine building, the replacement of main steam safety valves, the replacement of piping and valves in the liquid waste treating system, the replacement of piping in the feed heater drain system and so on. (Kako, I.)

  16. An annual report of the Japan Atomic Industrial Forum in 1998. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    Every year, the Japan Atomic Industrial Forum (JAIF) puts out a report on the current status of the world's nuclear power plants (NPPs). A report in this year was based on a survey of some 90 electric utilities worldwide, from 33 countries and regions. At the end of 1998, there were 422 NPPs operating around the world, which were seven fewer than those of last year. And, their combined capacity was 358.49 GW, which was 6.207 GW down from that of 1997. In addition, some 46 units were under construction with a combined capacity of 38.068 GW, compared with comparable figures of 43 units and 35.261 GW the year before. Furthermore, further 46 units were in planning stages, with their combined capacities of 34.488 GW. Two new power plants, Wolsong No.3 and Ulchin No.3 (both are in South Korea) entered commercial operation. This brings total numbers of NPPs in South Korea to 14, with a combined capacity of 12.016 GW, which pulls South Korea ahead of Canada and Sweden to the 8th position in the world. (G.K.)

  17. Latest knowledge on radiological effects. Radiation health effects of atomic bomb explosions and nuclear power plant accidents

    International Nuclear Information System (INIS)

    The latest knowledge encompass findings presented both in individual scientific publications and in internationally accepted reports. This review summarizes the latest knowledge on radiobiological effects on the latter level, using studies of atomic bomb survivors and victims of Chernobyl nuclear power plant accident. First of all, it is important to note that while examining individual patient, it is impossible to distinguish a radiation-induced cancer patient and non-radiation-induced cancer patient even when using state-of-the-art techniques. Therefore, investigation of radiation effects on humans, especially late health effects has been based on the epidemiological and statistical methods. Based on studies on atomic bomb survivors, it is well accepted that there is a linear increase in the risk of cancer with the increase of radiation dose. However, the existence of a threshold is a controversial issue, and health effects with regards to non-cancer diseases are not yet accepted by international authorities. Childhood thyroid cancer has increased after the Chernobyl accident and more than several thousands children are affected by it. However, there is no proof that any disease, with the exception of thyroid cancer and acute radiation effects, has increased after the Chernobyl accident. Finally, it should be mentioned that providing scientific explanation of the results to general public is an honorable duty of concerned scientists. (author)

  18. 78 FR 26401 - Connecticut Yankee Atomic Power Company, Haddam Neck Plant, Environmental Assessment and Finding...

    Science.gov (United States)

    2013-05-06

    ... Accession No. ML073250040). The HNP ISFSI is a vertical dry cask storage facility for spent nuclear fuel... placed all spent nuclear fuel and Greater-Than-Class-C waste into dry storage at an ISFSI on the HNP site... of Spent Fuel in NRC-Approved Storage Casks at Power Reactor Sites (55 FR 29181; July 18, 1990),......

  19. Nuclear power plants

    International Nuclear Information System (INIS)

    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.)

  20. Safety Evaluation Report related to the operation of Enrico Fermi Atomic Power Plant, Unit No. 2 (Docket No. 50-341). Supplement No. 4

    International Nuclear Information System (INIS)

    Supplement No. 4 to the Safety Evaluation Report related to the operation of the Enrico Fermi Atomic Power Plant, Unit 2, provides the staff's evaluation of additional information submitted by the applicant regarding outstanding review issues identified in Supplement No. 3 to the Safety Evaluation Report, dated January 1983

  1. Safety evaluation report related to the operation of Enrico Fermi Atomic Power Plant, Unit No. 2. Docket No. 50-341

    International Nuclear Information System (INIS)

    Supplement No. 3 to the Safety Evaluation Report related to the operation of the Enrico Fermi Atomic Power Plant, Unit 2, provides the staff's evaluation of additional information submitted by the applicant regarding outstanding review issues identified in Supplement No. 2 to the Safety Evaluation Report, dated January 1982

  2. In situ measurement of dynamic characteristics of atomic power plant equipment

    International Nuclear Information System (INIS)

    For the realistic assessment of stiffness and damping, full scale free vibration tests have been carried out on various pieces of equipment located in plant buildings both during the construction stage and after they are erected. Initial displacement or initial velocity was used to excite the free vibrations. Initial displacement was imparted by means of steel rope pulled with chain pulley block. The sudden release was achieved by means of a clutch system. Acceleration transducer with amplifier and ink writting oscillograph was used for recording the vibrations. Frequency and damping was evaluated from the acceleration records. Observed values for some equipment are given. For some equipment, it has been possible to obtain the values with and without pipe connections. The frequency of L.P. Heater in longitudinal and transverse directions without pipe connection were 17.86 and 10.04 Hz but with pipe connections the values increased to 26.74 and 17.85 Hz. Similarly there has been increase in the damping values too. Thus both the frequency and damping increases substantially with the addition of pipe connections. Moreover, their values are quite different in the two principal directions, pointing out to the importance of in situ measurements on prototype equipment

  3. International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

    International Nuclear Information System (INIS)

    This report presents the proceedings of the Specialist's Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately

  4. Tritium discharges into the atmosphere at the first and second blocks of the Leningrad V. I. Lenin Atomic Power Plant

    International Nuclear Information System (INIS)

    To study tritium discharges into the atmosphere from the first and second blocks (phase I) of the Leningrad V. I. Lenin Atomic Power Plant, from 1981 to 1985 the authors conducted several series (each lasting 1-2 months) of simultaneous observations of the specific tritium radioactivity in the coolant, cooling water of the control and safety system, and other in-house process water, and the volume radioactivity of tritium in the gas exiting the reactor plenum and in air discharged to the atmosphere through the special ventilation systems. In the measurement period they monitored the volume flow rate of the helium-nitrogen mixture through the reactor plenum, the volume flow rate of the air discharged through the chimney and pipes leading onto the roofs of the blocks, atmospheric humidity, and the moisture content of air discharged to the atmosphere through discharge pipes. The research was conducted with both blocks operating under near-nominal conditions. The paper presents the observational results for the series in 1981 and 1985, averaged for the two blocks

  5. CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station. Pt. 1. Validation for 2 power plant units in operation

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, P.K.; Goyal, P.; Markandeya, S.G. [Bhabha Atomic Research Centre, Trombay, Mumbai (India). Planning and Coordination Div.; Ghosh, A.K. [Bhabha Atomic Research Centre, Trombay, Mumbai (India). Health Safety and Environment Group

    2011-05-15

    The thermal pollution arising out of discharge of hot water from the power plant condensers into the natural water bodies such as rivers, lakes, reservoirs, oceans etc. has been a serious concern to environmentalists ever since the plants started operating world over. In the past forty to fifty years, the methods of calculations for predicting the velocity and temperature fields in the affected regions of the stagnant/flowing water bodies have undergone a significant improvement. Currently, use of Computational Fluid Dynamics (CFD) codes for performing these calculations is gaining popularity. However, several factors such as the assumed computational domain and its discretisation, the boundary conditions used, representation of hydrodynamic characteristics (laminar/turbulent, buoyant/non-buoyant), etc. have a strong influence on the accuracy of predictions by such a model. A CFD code STAR-CD has been used for analyzing the thermal plume behaviour in the Kadra reservoir at Kaiga Atomic Power Station (KAPS). The predictions from these calculations of two units in operation have been found to be in good agreement with the site data made available from earlier studies. The present paper briefly describes the model developed using STAR-CD and results obtained for the Kadra reservoir at KAPS. (orig.)

  6. CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station. Pt. 1. Validation for 2 power plant units in operation

    International Nuclear Information System (INIS)

    The thermal pollution arising out of discharge of hot water from the power plant condensers into the natural water bodies such as rivers, lakes, reservoirs, oceans etc. has been a serious concern to environmentalists ever since the plants started operating world over. In the past forty to fifty years, the methods of calculations for predicting the velocity and temperature fields in the affected regions of the stagnant/flowing water bodies have undergone a significant improvement. Currently, use of Computational Fluid Dynamics (CFD) codes for performing these calculations is gaining popularity. However, several factors such as the assumed computational domain and its discretisation, the boundary conditions used, representation of hydrodynamic characteristics (laminar/turbulent, buoyant/non-buoyant), etc. have a strong influence on the accuracy of predictions by such a model. A CFD code STAR-CD has been used for analyzing the thermal plume behaviour in the Kadra reservoir at Kaiga Atomic Power Station (KAPS). The predictions from these calculations of two units in operation have been found to be in good agreement with the site data made available from earlier studies. The present paper briefly describes the model developed using STAR-CD and results obtained for the Kadra reservoir at KAPS. (orig.)

  7. 78 FR 58571 - Maine Yankee Atomic Power Company, Connecticut Yankee Atomic Power Company, and The Yankee Atomic...

    Science.gov (United States)

    2013-09-24

    ... Atomic Power Company, Connecticut Yankee Atomic Power Company, and The Yankee Atomic Electric Company... Power Company (Maine Yankee), Connecticut Yankee Atomic Power Company (Connecticut Yankee), and the Yankee Atomic Electric Company (Yankee Atomic) (together, ``licensees'' or ``the Yankee Companies'')...

  8. Automatic power control system for 235 MWe atomic power reactor

    International Nuclear Information System (INIS)

    The paper highlights the essential features of the design, fabrication and testing of microprocessor based reactor power regulating system of Narora Atomic Power Plant (NAPP) and Kakrapar Atomic Power Plant (KAPP). The improved system design at KAPP employs the reactor power control based on neutron flux signal after correction. The control system responses have been presented and compared with the responses using a reactor functional simulator. A new fault tolerant reactor regulating system has been designed using a dual active and hot stand-by microprocessor system to improve operational reliability. (author). 1 ref., 8 figs

  9. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  10. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  11. 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...

  12. Correlation of level of vasoactive substances and disorder of cerebral hemodynamics in patients who took part in of the accident clean-up at Chernobyl Atomic Power Plant

    International Nuclear Information System (INIS)

    The study involved 166 participants of the accident clean-up at the Chernobyl Atomic Power Plant. Cerebral hemodynamics was investigated with trans cranial Doppler ultrasound along the middle cerebral artery. The observed changes can be regarded as one of the mechanisms forming postradiation cerebral dyscirculations which early development in the relatively young persons (under 40) can suggest increased rate of aging in the studied population

  13. Characteristic of lipid metabolism and state of free-radical processes in workers of 30-km alienation zone at Chernobyl Atomic Power Plant

    International Nuclear Information System (INIS)

    The study involved 54 men aged 35-50 working in 30 km alienation zone at the Chernobyl Atomic Power Plant. Blood serum and erythrocyte lipid peroxidation indices were estimated. Investigation of peroxidation processes in the erythrocytes allowed to reveal changes in glutation system, they being characterized by its amount elevation against the background of glutation transferase activity increase both in the persons, working in the 30 km zone, and in those from 'Ukryttia' Establishment

  14. 75 FR 63867 - DTE Energy; Enrico Fermi Atomic Power Plant Unit 1, Exemption From Certain Security Requirements

    Science.gov (United States)

    2010-10-18

    .... Nuclear Regulatory Commission (NRC or the Commission) now or hereafter in effect. Fermi 1 was a fast breeder reactor power plant cooled by sodium and operated at essentially atmospheric pressure. In November... in Monroe County, Michigan. Fermi 1 is a permanently shutdown nuclear reactor facility. The...

  15. Wind power plants

    Energy Technology Data Exchange (ETDEWEB)

    Stiller, W.

    1980-01-01

    Wind power plants have practically faded into oblivion in Germany. These wind power plants are systems converting wind power into other usable energy forms, mainly into electric current. The irregularity of wind currents requires storage of the energy produced. The cost situation is calculated for a small wind power plant.

  16. International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    This report presents the proceedings of the Specialist`s Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately.

  17. Confirmation methods for the disposal of filled-solidified waste drums from Tokai Nuclear Plant of Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Concentrated exhaust liquid and spent resins from nuclear power plants in operation are mixed with cement, asphalt or plastics to form solidified materials and filled in the 200 litter drums and to be disposed at Rokkasho Nuclear Fuel Reprocessing Plant. Japan Nuclear Energy Safety Organization (JNES) is in charge of confirmation of the adaptability and compliance of these wastes to the guidelines and regulations. The report contains the solidification using high-frequency melting furnace, filling methods of the solid wastes into the drums, and making a review and improvement for the confirmation. (S. Ohno)

  18. Field of the application and general project decisions of atomic thermal power plant ATETS-80 based on integral WWER type reactor

    International Nuclear Information System (INIS)

    Design Bureau of Machine Building is gradually being developed the direction of improvement WWER type reactors of the small and medium power for the production of heat and electricity. It is presented the integral WWER energetic reactor ATETS-80 in composition of thermal power plant, destined for the combined processing of electric power, steam, hot water, desalination of marine and pickling water. Electric power of the bloc ATETS-80 equal to 85 MWt, the heat power equal to 250 MWt. The project ATETS-80 of the promoted safety worked out on base of common project decisions, established and worked for reactor installations WWER, atomic icebreakers and general atomic plants of heat deliveries. General project decisions: integral accomplishment of the reactor; ramjet steam generator with superheating; two loops of exchange heat with channels of ECCS; autonomous channel ECCS on reactor; insurance vessel, discharged to full emergency pressure in case of the rupture of first contour; the containment shell, provided the protection from external effects. 2 figs

  19. Power Plant Cycling Costs

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, N.; Besuner, P.; Lefton, S.; Agan, D.; Hilleman, D.

    2012-07-01

    This report provides a detailed review of the most up to date data available on power plant cycling costs. The primary objective of this report is to increase awareness of power plant cycling cost, the use of these costs in renewable integration studies and to stimulate debate between policymakers, system dispatchers, plant personnel and power utilities.

  20. Hydroelectric Power Plants Dobsina

    International Nuclear Information System (INIS)

    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

  1. Radiation situation and irradiation level in forest workers in places of timber works in alienation zone of Chernobyl Atomic Power Plant

    International Nuclear Information System (INIS)

    The radiation hygienic situation in the forest plots and dose load of the personnel at timber works in the alienation zone of the Chernobyl Atomic Power Plant was evaluated.It has been revealed that the density of contamination of the forest soil at the areas of timber works was 155.4-447.3 kBq centre dot m2. Maximum year equivalent dose on the lungs and total dose of external and internal irradiation in the forest workers in the zone of alienation during the work at the areas were about 40% of the values of the respective dose limits for the population of B category

  2. Small hydroelectric power plants

    International Nuclear Information System (INIS)

    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

  3. Solar thermal power plants

    International Nuclear Information System (INIS)

    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)

  4. 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)

  5. 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

  6. Nuclear power plant simulator

    International Nuclear Information System (INIS)

    In this paper, real time nuclear power plant simulator for student education is described. The simulator is composed of a hybrid computer and an operating console. Simulated power plant is a 36 MWt PWR plant, and the average temperature of the primary coolant within the reactor is controlled to be constant. Reactor Kinetics, fuel temperature, primary coolant temperature, temperature and pressure of steam within the steam generator, steam flow, control rod driving system, and feed water controlling system are simulated. The use of the hybrid computer made it possible to simulate a relatively large scale power plant with a comparatively small size computing system. (auth.)

  7. Nuclear power plant construction

    International Nuclear Information System (INIS)

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

  8. 135Cs activity and 135Cs/137Cs atom ratio in environmental samples before and after the Fukushima Daiichi Nuclear Power Plant accident

    Science.gov (United States)

    Yang, Guosheng; Tazoe, Hirofumi; Yamada, Masatoshi

    2016-04-01

    135Cs/137Cs is a potential tracer for radiocesium source identification. However, due to the challenge to measure 135Cs, there were no 135Cs data available for Japanese environmental samples before the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident. It was only 3 years after the accident that limited 135Cs values could be measured in heavily contaminated environmental samples. In the present study, activities of 134Cs, 135Cs, and 137Cs, along with their ratios in 67 soil and plant samples heavily and lightly contaminated by the FDNPP accident were measured by combining γ spectrometry with ICP-MS/MS. The arithmetic means of the 134Cs/137Cs activity ratio (1.033 ± 0.006) and 135Cs/137Cs atom ratio (0.334 ± 0.005) (decay corrected to March 11, 2011), from old leaves of plants collected immediately after the FDNPP accident, were confirmed to represent the FDNPP derived radiocesium signature. Subsequently, for the first time, trace 135Cs amounts before the FDNPP accident were deduced according to the contribution of global and FDNPP accident-derived fallout. Apart from two soil samples with a tiny global fallout contribution, contributions of global fallout radiocesium in other soil samples were observed to be 0.338%–52.6%. The obtained 135Cs/137Cs database will be useful for its application as a geochemical tracer in the future.

  9. (135)Cs activity and (135)Cs/(137)Cs atom ratio in environmental samples before and after the Fukushima Daiichi Nuclear Power Plant accident.

    Science.gov (United States)

    Yang, Guosheng; Tazoe, Hirofumi; Yamada, Masatoshi

    2016-01-01

    (135)Cs/(137)Cs is a potential tracer for radiocesium source identification. However, due to the challenge to measure (135)Cs, there were no (135)Cs data available for Japanese environmental samples before the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident. It was only 3 years after the accident that limited (135)Cs values could be measured in heavily contaminated environmental samples. In the present study, activities of (134)Cs, (135)Cs, and (137)Cs, along with their ratios in 67 soil and plant samples heavily and lightly contaminated by the FDNPP accident were measured by combining γ spectrometry with ICP-MS/MS. The arithmetic means of the (134)Cs/(137)Cs activity ratio (1.033 ± 0.006) and (135)Cs/(137)Cs atom ratio (0.334 ± 0.005) (decay corrected to March 11, 2011), from old leaves of plants collected immediately after the FDNPP accident, were confirmed to represent the FDNPP derived radiocesium signature. Subsequently, for the first time, trace (135)Cs amounts before the FDNPP accident were deduced according to the contribution of global and FDNPP accident-derived fallout. Apart from two soil samples with a tiny global fallout contribution, contributions of global fallout radiocesium in other soil samples were observed to be 0.338%-52.6%. The obtained (135)Cs/(137)Cs database will be useful for its application as a geochemical tracer in the future. PMID:27052481

  10. Radioecological investigation of soil and plant cover at the neighvouring landscape areas in the zone surroimding Chernobyl' atomic power station

    International Nuclear Information System (INIS)

    A study was made on content levels and regularities of radionuclide migration in soil and plant cover at the neighbouring landscape areas in 30-km zone of Chernobyl accident. Quantitative estimation of radionuclide distribution in main components of soil and plant cover is given. Possibility of self-purification of some, most dynamic areas of geochemical integration is shown

  11. Technology and power plants

    International Nuclear Information System (INIS)

    In this paper the contributions presented at the 18th IAEA Fusion Energy Conference in the field of technology and power plants are summarised with reference to the following distinct issues: ITER EDA Design, ITER Technology R and D, Progress Towards Advanced Performance and Steady State, Compact Cu Burning Plasma Experiments and Neutron Sources, Advanced Materials Research, Power Plant Design and Economic Forecasts, and Conclusions

  12. Power plants 2010. Lectures

    International Nuclear Information System (INIS)

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

  13. Power plant at sea

    International Nuclear Information System (INIS)

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

  14. Nuclear power plant outages

    International Nuclear Information System (INIS)

    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

  15. LNG plant combined with power plant

    International Nuclear Information System (INIS)

    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

  16. Power plants 2002. Lectures

    International Nuclear Information System (INIS)

    Main topics of the meeting: Power economy for the Eastern European countries and their economical growth during overtaking by utilities; climatic change by fossil-fuel power plants; deregulation and competition challenges; cogeneration from fossil fuels and renewable energy sources; research programs for advanced energy systems and problems of certification and regulations; power trade and influence on the operators; air pollution and kyoto protocol and climatic change between policy and engineering tasks. (GL)

  17. Kruemmel nuclear power plant

    International Nuclear Information System (INIS)

    This short description of the site and the nuclear power plant with information on the presumable effects on the environment and the general public is to provide some data material to the population in a popular form so that the citizens may in form themselves about the plant. In this description which shall be presented to the safety report, the site, the technical design and the operation mode of the nuclear power plant are described. Some problems of the emission and the effects of radioactive materials as well as other issues related to the plant which are of interest to the public are dealt with. The supposed accidents and their handling are discussed. The description shows that the selected site is suitable for both setting-up and operation of the plant without affecting the safety of the people living there and that in admissible burdens of the environment shall not have to be expected. (orig./HP)

  18. FINAL–REPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004)

    Energy Technology Data Exchange (ETDEWEB)

    Erika Bailey

    2011-07-07

    The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963.

  19. Multiplex Tokamak power plant

    International Nuclear Information System (INIS)

    The concept of multiplexing for a fusion power core as an option for producing power is explored. Superconducting, as well as normal magnet, coils in either first or second stability regimes are considered. The results show that multiplex plants with superconducting magnets operating in the second stability regime could be competitive with the single-unit plants in some unit sizes. The key issues that impact the expected benefits of multiplexing must be investigated further. These are factory fabrication, economy of scale, the extent of equipment sharing, inherent safety, maintainability, and utility load management

  20. The state of lipid metabolism in liquidators at long terms after the accident at Chornobyl Atomic Power Plant

    International Nuclear Information System (INIS)

    The spectrum of lipids in the blood serum in 202 men aged 35-55 who participated in the Chornobyl accident clean-up. All of them worked at the plant in 1986-1987 and receive total dose of 10-25 cGy. All the patients were divided into two age groups, 35-44 years old and 45-55 years old. The character of lipid and lipoprotein spectrum changes suggests marked atherosclerotic changes in the young age group. Thus, the risk of early atherosclerosis is higher in persons exposed to low-dose ionizing radiation in an early age which necessitates more careful investigation of the lipid spectrum in this group during the check-ups

  1. GEOTHERMAL POWER GENERATION PLANT

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, Tonya

    2013-12-01

    Oregon Institute of Technology (OIT) drilled a deep geothermal well on campus (to 5,300 feet deep) which produced 196oF 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.

  2. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

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

  3. Report concerning Zarnowiec nuclear power plant

    International Nuclear Information System (INIS)

    Report of the Team of the President of the National Atomic Energy Agency regarding Zarnowiec nuclear power plant contains the analysis of situation in Poland in June 1990, the assessment of public opinion, as well as the description of ecological, technical and economical problems. The team's conclusions are given together with the general conclusion to stop the construction of Zarnowiec nuclear power plant. 5 appendixes, 6 enclosures, 1 documents list, 1 tab. (A.S.)

  4. Power plant process computer

    International Nuclear Information System (INIS)

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

  5. Miniature thermoelectric power plant

    OpenAIRE

    Moreira, António H. J.; Freitas, Ricardo; Esteves, João Sena

    2006-01-01

    This paper describes a miniature thermoelectric power plant made with the boiler and the water pump from an old starch iron. It also uses a computer cooling fan, which serves as electric power generator. The boiler vaporizes the water it receives from the water pump. Then, the steam is injected over the turbine of the fan making it twirl. The voltage generated by the fan is enough to lighten a couple of LEDs. A wooden case with a chimney encloses all the referred devices.

  6. Miniature thermoelectric power plant

    OpenAIRE

    Moreira, António, 1957-; Freitas, Ricardo; Sepúlveda, João; Esteves, João Sena

    2010-01-01

    This paper describes a miniature thermoelectric power plant made with the boiler and the water pump from an old starch iron. It also uses a computer cooling fan, which serves as electric power generator. The boiler vaporizes the water it receives from the water pump. Then, the steam is injected on the turbine of the fan, making it twirl. The voltage generated by the fan is enough to lighten a couple of LEDs. A wooden case with a chimney encloses all the referred devices.

  7. Nuclear turbine power plant

    International Nuclear Information System (INIS)

    Purpose : To improve the heat cycle balance in a nuclear turbine power plant or the like equipped with a moisture separating and reheating device, by eliminating undesired overcooling of the drains in the pipes of a heat transmission pipe bundle. Constitution : A high pressure turbine is driven by main steams from a steam generator. The steams after driving the high pressure turbine are removed with moistures by way of a moisture separator and then re-heated. Extracted steams from the steam generator or the high pressure turbine are used as a heating source for the reheating. In the nuclear turbine power plant having such a constitution, a vessel for separating the drains and the steams resulted from the heat exchange is provided at the outlet of the reheating device and the steams in the vessel are introduced to the inlet of the moisture separator. (Aizawa, K.)

  8. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To suppress corrosion at the inner surfaces of equipments and pipeways in nuclear power plants. Constitution: An injection device comprising a chemical injection tank and a plunger type chemical injection pump for injecting hydrazine as an oxygen remover and ammonia as a pH controller is disposed to the downstream of a condensate desalter column for primary coolant circuits. Since dessolved oxygen in circuit water injected with these chemicals is substantially reduced to zero and pH is adjuted to about 10 - 11, occurrence of stress corrosion cracks in carbon steels and stainless steels as main constituent materials for the nuclear power plant and corrosion products are inhibited in high temperature water, and of corrosion products are inhibited from being introduced as they are through leakage to the reactor core, by which the operators' exposure does can be decreased significantly. (Sekiya, K.)

  9. Nuclear power plants

    International Nuclear Information System (INIS)

    Before the economical adaptability of nuclear power plants was achieved, many ways were tried to technically use nuclear fission. In the course of a selection process, of numerous types of reactors, only a few have remained which are now taking part in the competition. The most important physical fundamentals, the occurence of various reactor concepts and the most important reactor types are the explained. (orig./TK)

  10. Nuclear power plant erection

    International Nuclear Information System (INIS)

    The erection of a nuclear power plant covers all the installation operations related to mechanical and electrical equipment in buildings designed for this specific purpose. Some of these operations are described: erection of the nuclear boiler, erection work carried out in the building accomodating the nuclear auxiliary and ancillary equipment and the methods and the organization set up in order to carry out this work satisfactorily are analyzed

  11. Power plant emissions reduction

    Science.gov (United States)

    Anand, Ashok Kumar; Nagarjuna Reddy, Thirumala Reddy

    2015-10-20

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

  12. Power plant design model

    International Nuclear Information System (INIS)

    This paper reports on the Power Plant Design Model (PPDM) which is an interactive FORTRAN/2020 program with over 15,000 lines of code that allows a user to create an engineering model of a grass roots solid fuel-fired facility capable of generating steam for electrical power generation and/or sale. Capital, operating, and maintenance cost estimates of the modeled plant are also generated. The model's technical output contains complete material and energy balances of all major streams, parasitic power calculations, boiler operating data and a major equipment list. The economic output consists of a capital cost estimate for the plant in a spreadsheet format detailing the material, labor and indirect costs associated with each piece of equipment. The model was intended for use as a marketing tool to replace engineering feasibility studies which are needed to determine the viability of a project. The model provides preliminary economics at a fraction of time and manpower effort normally associated with this task

  13. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    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.)

  14. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    In 1973 the 345 MW pressurized water nuclear power plant at Obrigheim operated on base load, generating approximately 2.63 TWh, approximately 2.5 TWh of which was supplied to the KWO members. The plant availability for the year was 89.9%. Of the 10.1% non-availability, 6.4% (23 d) was caused by refuelling, including inspection, overhaul and repair operations and routine tests carried out in September 1973. 3.3% was due to stoppages for repairs to a steam generator and the two main cooling pumps, while 0.4% resulted from failures in the electrical section of the plant. The plant was shut down seven times in all, including three scrams. The average core burnup at the end of the fourth cycle (1 September 1973) was 18900 MWd/tU, representing an average burnup of approximately 37500 MWd/tU for a fuel element used in all four cycles. The operating performance of the steam generators and the result of the steam generator inspection carried out during refuelling in 1973 suggest no progressive damage. The quantities of radioactive materials released to the environment in 1973 were well below the officially permitted levels. The availability of the plant from the beginning of pilot operation in 1969 to the end of 1973 was 83.7 %

  15. Initiative against nuclear power plants

    International Nuclear Information System (INIS)

    This publication of the Initiative of Austrian Nuclear Power Plant Opponents contains articles on radiactive waste dispoasal in Austria and and discusses safety issues of the nuclear power plant 'Zwentendorf'. (kancsar)

  16. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    The gross output of the 345MWe pressurized water nuclear power station at Obrigheim, operation on base load, amounted to about 2.57TWh in 1974, the net power fed to the grid being about 2.44TWh. The core was used to its full capacity until 10 May 1974. Thereafter, the reactor was on stretch-out operation with steadily decreasing load until refuelled in August 1974. Plant availability in 1974 amounted to 92.1%. Of the 7.9% non-availability, 7.87% was attributable to the refuelling operation carried out from 16 August to 14 September and to the inspection, overhaul and repair work and the routine tests performed during this period. The plant was in good condition. Only two brief shutdowns occurred in 1974, the total outage time being 21/2 hours. From the beginning of trial operation in March 1969 to the end of 1974, the plant achieved an availability factor of 85.2%. The mean core burnup at the end of the fifth cycle was 19600 MWd/tonne U, with one fuel element that had been used for four cycles achieving a mean burnup of 39000 MWd/tonne U. The sipping test on the fuel elements revealed defective fuel-rods in a prototype plutonium fuel element, a high-efficiency uranium fuel element and a uranium fuel element. The quantities of radioactive substances released to the environment in 1974 were far below the officially permitted values. In july 1974, a reference preparation made up in the nuclear power station in October 1973 was discovered by outsiders on the Obrigheim municipality rubbish tip. The investigations revealed that this reference preparation had very probably been abstracted from the plant in October 1973 and arrived at the rubbish tip in a most irregular manner shortly before its discovery

  17. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  18. Once again: A nuclear power plant shut down - causes and consequences of the lack of relevant licences issued under Air Pollution Control Law, parallel to the (partial) construction licences required for nuclear power plants under the Atomic Energy Act

    International Nuclear Information System (INIS)

    For the first time, a Federal German court has decided to shut down a nuclear power station (Muelheim-Kaerlich) that has been operating since then on the basis of valid operating licenses issued by the competent licensing authority (OVG Koblenz, Higher administrative court, decision 7 B II 2/86 of October 10, 1986). The article discusses the legal problems created by this decision, as e.g.: The factual scope of validity of a licence granted under section 7 Atomic Energy Act; the protection of confidence of the applicant for a licence in connection with the self-engagement of the licensing authority; consideration of the non-licensed cooling tower in the preliminary proceedings for guaranteeing legal protection. The author backs the decision of the OVG Koblenz, as a nuclear power station may not start operation without a licence issued under air pollution control laws, which in this case had not yet been obtained. (HSCH)

  19. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

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

  20. Floating nuclear power plants

    International Nuclear Information System (INIS)

    This article examines the legal regime for floating nuclear power plants (FNPs), in view of the absence of specific US legislation and the very limited references to artificial islands in the Law of the Sea Convention. The environmental impacts of FNPs are examined and changes in US regulation following the Three Mile Island accident and recent US court decisions are described. References in the Law of the Sea Convention relevant to FNPs are outlined and the current status of international law on the subject is analysed. (author)

  1. Demonstration tokamak power plant

    Energy Technology Data Exchange (ETDEWEB)

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

    1983-01-01

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

  2. Citizens contra nuclear power plants

    International Nuclear Information System (INIS)

    Is Wyhl the beginning of a new citizens' movement against official policies concerning atomic energy or is it the end of citizens' initiatives of latter years. Did democracy pass its test in Wyhl, or was the state's authority undermined. The danger of atomic energy was not the only concern of the citizens of the Rhine valley who demonstrated against the planned nuclear power plant, but also the quality of industrial and energy planning in which the democratic foundations have to be safeguarded. In the meantime, the doubts increase that this source of energy is of a not dangerous nature, and the myth of supposedly cheap atomic energy has been scattered. The dangers in connection with waste transport and storage were made public beyond the boundaries of the places in question, in particular as a result of the demonstrations. The publication documents the course of the demonstration and the site occupation from the beginning of Febuary 1975 onwards. The occupation still continued when the booklet was published despite the decision of the Administrative Court in Freiburg at the end of March (prohibition of commencement of building until the verdict on the principal suit against the overall project has been reached, the final decision to be made by the Higher Administrative Court in Mannheim). The author aims at describing the new quality of citizens' commitments in this booklet. (orig./LN)

  3. Civil engineering for power plants

    International Nuclear Information System (INIS)

    Power plant structures are conspicuously visible and have an impact on our landscape. In the opinion of a critical public, a successful external design can greatly enhance acceptance of an undertaking and its plants. This paper considers the subjects - utilization of by-products, aggregation of series experience in the construction of nuclear power plants, architecture in power plant construction, water works for adequate cooling water supply and also quality assurance in civil engineering and optimum application of electronic data processing. (orig.)

  4. Energy balances for power plants

    International Nuclear Information System (INIS)

    An important aspect of a power plant is its energy balance, i.e. the electrical energy produced by the plant over its overall operation period, compared to the amount of non-renewable energy used to create and build the plant. Tense discussions took place in the past between criticizers and promotors of a given technology, some technologies even being accused of having a negative energy balance. Mostly based on built examples the present study aims at giving objective data for the represented technologies, as follows: a 64 MW hydro power plant in the Alps, with seasonal water storage in a lake; a 60 MW run-of-river high-head hydro power plant in the Alps; two run-of-river low-head hydro power plants in the Swiss Midlands (14 MW and 25 MW respectively); a small 30 kW wind power generator located near the Simplon Pass at 2000 m over sea level, in the Alps; a 3 kW photovoltaic generator in the roof of a single-family house; a 500 kW photovoltaic power plant in the Jura, at 1000 m over sea level; a 0.9 MWel/8.8 MWtherm fossil-fuel co-generation plant near Zuerich; a 200 MW natural-gas-fired gas/vapour turbine power plant; a 300 MW heavy-fuel-fired power plant; a 500 MW coal-fired power plant; and the Leibstadt 990 MW nuclear power plant. The best energy balances are obtained for the hydro power plants, the worst for the Leibstadt nuclear power plant. In between the photovoltaic plants and the fossil-fuel-fired plants are found. The figures differ by more than two orders of magnitude

  5. Nuclear Power Plant 1996

    International Nuclear Information System (INIS)

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

  6. Atucha I nuclear power plant surveillance programme

    International Nuclear Information System (INIS)

    After a review of the main characteristics of the Atucha I nuclear power plant and its pressure vessel, the embrittlement surveillance capsules and the irradiation conditions are described; Charpy impact tests and tensile tests were performed on the irradiated samples, and results are discussed and compared to theoretical calculations: transition temperature shifts, displacement per atom values. 6 refs., 16 figs., 7 tabs

  7. MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

    Czech Academy of Sciences Publication Activity Database

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

    2015-01-01

    Roč. 164, č. 4 (2015), s. 519-522. ISSN 0144-8420 Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.913, year: 2014

  8. Modelling of nuclear power plant decommissioning financing

    Czech Academy of Sciences Publication Activity Database

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

    Vol. 2015. Oxford: Oxford Journals, 2015, s. 1-4. ISSN 1742-3406. [8th International Conference on High Levels of Natural Radiation and Radon Areas (ICHLNRRA 2014). Prague (CZ), 01.09.2014-05.09.2014] Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders

  9. Power Plant- A Scientific Disaster

    Directory of Open Access Journals (Sweden)

    Dharmateja Bandlamudi, Sahithi Avirneni

    2013-05-01

    Full Text Available The present paper emphasisesthe society’s movement towards improvement of power sector as a pavement of luxury and on the benighted dark side of it. This produces the reasons for enchanting power plant as a scientific disaster. This paper gives the detailed list of effects caused by the power plants mainly on coal fired, nuclear and hydroelectric power plants, their adverse effects on environment and in turn human life.

  10. Occupational exposure management at nuclear power plants

    International Nuclear Information System (INIS)

    The Information System on Occupational Exposure (ISOE), a joint initiative of the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA), has become a unique worldwide programme on the protection of workers in nuclear power plants, including a network for the exchange of experience in the area of occupational exposure management, and the world's largest database on occupational exposure from nuclear power plants. Each year, an international workshop or symposium offers a forum for radiation protection professionals from the nuclear industry, operating organisations and regulatory authorities to exchange information on practical experience with occupational radiation exposure issues in nuclear power plants. These proceedings include the presentations made at the Third ISOE European Workshop on Occupational Exposure Management at Nuclear Power Plants, held in April 2002 in Portoroz, Slovenia. (author)

  11. 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.

  12. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

    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. Combined cycle power plant Skopje

    International Nuclear Information System (INIS)

    Regarding the new directions in constructing combined cycle power plants, in this work an idea of such plant in Skopje with power of 190 MW has been elaborated. This plant will be constructed on the site of the existing TPP 'Energetika', AD ESM. The rates of efficiency for different condition of operation has been estimated. (Author)

  14. Hybrid combined cycle power plant

    International Nuclear Information System (INIS)

    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)

  15. Power plant removal costs

    International Nuclear Information System (INIS)

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

  16. Power Plant Replacement Study

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Gary

    2010-09-30

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

  17. Power Plant Replacement Study

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Gary

    2010-09-30

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

  18. Nuclear power plant

    International Nuclear Information System (INIS)

    The present invention provides a nuclear power plant which generates thermoelectric power by utilizing heat generated by fission reaction. Namely, a fuel/thermoelectric material is made of a semiconductor material containing fission products or a semimetal material containing fission products. A reactor container contains the fuel/thermoelectric material and a reactor core constituted by the fuel/thermoelectric material. The reactor container comprises coolants for removing heat generated by nuclear reaction of fission products from the reactor core and a high temperature side electrode connected to a central portion of the fuel/thermoelectric material and a low temperature side electrode connected to the outside of the fuel/thermoelectric material. Electromotive force is caused in the fuel/thermoelectric material by temperature difference upon combustion caused at the central portion and the outer surface of the fuel/thermoelectric material. The electromotive force is taken out of the high temperature side electrode and the low temperature side electrode. (I.S.)

  19. Increase of power plant efficiency

    International Nuclear Information System (INIS)

    The increase of power plant efficiency has always been the aim of power plant manufacturers and operators. Today, after the re-orientation of the worldwide market situation, it is necessary to newly assess the power plant efficiency in the field of competition and environment. The average efficiency of power plants presently ranges worldwide at about 30%, yet the status of available technology in the year 2000 permits efficiencies between 45 an 58% depending on the fuels used. VGB PowerTech has been monitoring the technical development of power generation for 80 years up to now. From our point of view, power plant technology still has a great development potential at its disposal. (orig.)

  20. Atomic power in space: A history

    International Nuclear Information System (INIS)

    ''Atomic Power in Space,'' a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. 19 figs., 3 tabs

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

    International Nuclear Information System (INIS)

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

  2. Brighter for small power plants

    International Nuclear Information System (INIS)

    The article presents a small tunnel drilling machine aimed at using for the construction of small hydroelectric power plants and mentions briefly some advantages economically and environmentally of both the machine and the power production solution

  3. Public notice concerning the compilation of technical specifications and other information to be taken into account in the licensing and inspection of nuclear power plants pursuant to Atomic Energy Law

    International Nuclear Information System (INIS)

    In order to facilitate and to standardize procedures in the licensing and inspection of nuclear power plants under the Atomic Energy Law, this compilation shows the full range of data and information to be taken into account by the relevant authorities or by experts acting on behalf of the authorities in accordance with section 20 of the Atomic Energy Act in the process of examining the licensing requirements, as stated in section 7, sub-section 2 of the At. En. Act, or within the framework of public supervision of the construction or operation of nuclear power plants, as laid down in section 19 of At.En. Act. The information refers to: Site selection; PWR reactor containments made of steel; BWR reactor containments with pressure suppression system; reactor core and control elements with drives, pressurized containment; interials of the reactor containment; emergency cooling and RHR systems, including shutdown cooling; auxiliary systems of the reactor cooling system; equipment for the handling and storage of fuel elements; equipment and systems for the handling and storage of other radioactive substances as well as auxiliary reactor systems, ventilating systems; steam generating systems; steam turbine systems; cooling water systems as well as power plant auxiliary and accessory systems; electrical energy supply of the safety system; alarm systems, personal signalling system and communication systems; instrumentation and control technology, control rooms, emergency control point and selected control areas; reactor safety system; radiation protection and activity control. (orig./HP)

  4. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    The list indicates percentage ownership of commercial nuclear power plants by utility companies as of September 1, 1982. The list includes all plants licensed to operate, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review. Part I lists plants alphabetically with their associated applicants and percentage ownership. Part II lists applicants alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses

  5. Nuclear power plant database internet version

    International Nuclear Information System (INIS)

    The nuclear power plant database contains the design information on 50 domestic light-water reactor nuclear power plants retrieved from the safety analysis reports. Its version for the main frame computer in the Japan Atomic Energy Research Institute (JAERI) was opened to the public in 1995. In the present Internet version, approximately 64,000 data were retrieved from the main frame version and stored. These data include the shapes, dimensions, performances, etc. of the equipment and components described in 'Appendix 8: Safety design of the reactor facility' of each safety analysis report. This report describes the database structure, program specification and information retrieval functions of the Internet version. (author)

  6. Ageing management in German nuclear power plants

    International Nuclear Information System (INIS)

    In Germany the term ageing management comprises several aspects. A demand for a special 'ageing monitoring' programme is not explicitly contained in the regulations. However, from the Atomic Energy Act and its regulations results the operator's obligation to perform extensive measures to maintain the quality of the plant and the operating personnel working in the plant. From this point of view, comprehensive ageing management in German nuclear power plants has taken place right from the start under the generic term of quality assurance. (orig.)

  7. Ageing management in German nuclear power plants

    International Nuclear Information System (INIS)

    In Germany, the term 'ageing management' comprises several aspects. A demand for a special ageing monitoring programme is not explicitly contained in the regulations. However, from the Atomic Energy Act and its regulations results the operator's obligation to perform extensive measures to maintain the quality of the plant and the operating personnel working in the plant. From this point of view, comprehensive ageing management in German nuclear power plants has taken place right from the start under the generic term of quality assurance. (author)

  8. Microwave Power Standard using Cold Atoms

    CERN Document Server

    Paulusse, D C; Michaud, A; Paulusse, David C; Rowell, Nelson L; Michaud, Alain

    2003-01-01

    We discuss how the observation of Rabi flopping oscillations in a laser cooled atomic sample could be used as a microwave power standard. The rubidium atoms are first trapped in a standard MOT, then optically pumped, and dropped. As they enter the interaction region, a resonant pulsed microwave field is applied. Following the interaction lasting up to 10 ms, a probe laser beam is turned on and the fluorescence measures the population inversion.

  9. Polymeric materials for atomic power industry

    International Nuclear Information System (INIS)

    In the atomic power industry such as nuclear power generating stations, organic polymeric materials are widely used. Those materials have superior properties for electric insulation, for the fabricability and flexibility, so they are conveniently used from the viewpoint of economics too. Here, it is important to recognize the limit of their usage. The first chapter deals with the introduction of the polymeric materials for atomic power industry, i.e. their limiting usage under irradiation, and type test of the equipments. The second chapter describes the testing of the flamability of wire and cable which is mostly concerned at present. The third chapter introduces the accident at the Three Mile Island Nuclear Power Generating Station, which accident has given strong shock in the world, and the last chapter tells the fire accident at the Browns Ferry Nuclear Power Generating Station, which accident has accelerated the development of the fire resistant polymers. (author)

  10. How dangerous are atomic power stations?

    International Nuclear Information System (INIS)

    This article takes a look at potential dangers presented by atomic power stations and measures taken to ensure safety. Since the accident in Chernobyl, atomic power stations represent, from the point of view of the general public, a considerable danger. The article analyses the actual risks presented by atom power stations and asks the question, if these risks can even be assessed. Basic considerations on the stability and safety of reactors are discussed. Safety precautions implemented for the world's first nuclear reactor in the USA are discussed. The various safety precautions taken for various types of reactor are examined in detail. Also, the dangers presented by emissions that occur during normal operation are examined. The danger of a nuclear meltdown caused by external factors such as earthquakes, fire, aircraft crashes and terrorist activity is discussed

  11. Producing Electricity in Power Plant

    OpenAIRE

    Khabrana, Ahmed; Ageeli, Jaber

    2015-01-01

    Abstract This Bachelor thesis has been written at the Blekinge Institute of Technology. The thesis describes electricity production in Shoaiba Steam Power plant in Saudi Arabia. Shoaiba Power Plant is located 100 km South of Jeddah city in Saudi Arabia. Total power production ability reaches 4400 MW. Shoaiba Power Plant has two stages and is constructed with 11 units, each unit produces 400 MW at line voltage 24 kV and line current 16 kA. Main pieces of equipment and their function in the sta...

  12. AND THERMAL POWER PLANTS

    Directory of Open Access Journals (Sweden)

    Alduhov Oleg Aleksandrovich

    2012-10-01

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

  13. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    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

  14. Geological and geotechnical aspects of the foundation pit of Kaiga atomic power plant reactor building 2, Kaiga, Uttara Kannada district, Karnataka

    International Nuclear Information System (INIS)

    In India Nuclear Power Plants are constructed as per the guidelines laid by IAEA and AERB. Before concrete is poured into reactor building pits, they are systematically mapped and Iithostructural maps are prepared for pit base and side walls. The constraints noticed are carefully attended with geotechnical solutions and remedies to make foundation safe for the entire period of reactor life. Similarly, pit of Kaiga Reactor Building II was systematically mapped for circular base and side walls. Geo-engineering solutions like scrapping out loose, foliated schistose patches, scooping out soft altered zones, filling with grouting, rock-bolting rock segments with major joints and fractures for stopping seepage points were suggested. (author)

  15. Atomic power in space: A history

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    ''Atomic Power in Space,'' a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. 19 figs., 3 tabs.

  16. Atomic Power in Space: A History

    Science.gov (United States)

    1987-03-01

    "Atomic Power in Space," a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. Interplanetary space exploration successes and achievements have been made possible by this technology, for which there is no known substitue.

  17. Alloy Design for a Fusion Power Plant

    OpenAIRE

    Kemp, Richard

    2006-01-01

    Fusion power is generated when hot deuterium and tritium nuclei react, producing alpha particles and 14 MeV neutrons. These neutrons escape the reaction plasma and are absorbed by the surrounding material structure of the plant, transferring the heat of the reaction to an external cooling circuit. In such high-energy neutron irradiation environments, extensive atomic displacement damage and transmutation production of helium affect the mechanical properties of materials. Among these effect...

  18. Obligatory provisions for nuclear power plants

    International Nuclear Information System (INIS)

    To cover the expenses associated with decommissioning and disposal of their nuclear power plants, German nuclear power plant operators set aside a total of more than EUR 30 billion and entered the respective provisions into their balance sheets. One point of eminent importance in this regard is the question whether these provisions are adequate in amount and permitted under accounting and tax laws. The other point to be considered is whether the funds will be available reliably if and when needed. Against the backdrop of these issues, the practice and importance of making these provisions are described. This is followed by an outline of the basic accounting and taxation aspects. It is seen that obligations under public law can be the basis of financial provisions only if there is a obligation sufficiently concrete in terms of time and object. The following examination of applicable obligations under the Atomic Energy Act incumbent upon nuclear power plant operators with regard to decommissioning and disposal results in the finding that such obligations are only partly regulated in the Atomic Energy Act, and that specifications in terms of time and purpose are insufficient. If the national practice of making financial provisions is to be put on a reliable basis, it is recommended to express the law on decommissioning and its mode of financing in more concrete terms in the Atomic Energy Act. In addition to unequivocal decommissioning and disposal obligations, the Atomic Energy Act should also incorporate regulations about financial provisions for decomissioning which are in need of more precise language. The present practice of making provisions is characterized by the risk that the funds necessary for planned decommissioning and disposal may not be available when needed. It is against this background that possible solutions reducing that risk are discussed. A recommendation is expressed to establish a public fund for decommissioning and disposal to which the

  19. Hierarchical data visualization for atomic plant data

    International Nuclear Information System (INIS)

    This paper introduces our own hierarchical data visualization technique, HeiankyoView, and discusses its potential for fluid science. HeiankyoView represents hierarchy as nested rectangles, and displays thousands of data elements in one display space. The paper briefly introduces the algorithm and various applications of HeiankyoView, and discusses our attempts for visualization of computational fluid dynamics data. Finally, the paper introduces our work on visualization of atomic plant data using HeiankyoView. (author)

  20. 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

  1. Lessons of the Chernobyl Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Insensitivity of radiation without measuring apparatus and health outcome observed in the atomic bomb survivors of Hiroshima and Nagasaki are major sources that make people fear the possible late effects of radiation exposure attributable to nuclear power plant accident. However, the health conditions of people in the last 20 years around Chernobyl indicated the necessity to review the risk assessment suggesting that effects of radiation exposure may considerably be different between the atomic bombing and nuclear power plant accident. (author)

  2. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    The listing indicates percentage ownership of commercial nuclear power plants by utility companies as of August 15, 1977. The list includes all plants operating, under construction, docketed 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 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. Part I lists plants alphabetically with their associated applicants and percentage ownership. Part II lists applicants alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses

  3. The Mecca Biomass Power Plant

    International Nuclear Information System (INIS)

    Colmac Energy, Inc. is constructing a 47 MW biomass-fired, electrical power generating plant in Mecca, California. Commercial operation is scheduled for April, 1992. Electrical power will be sold to Southern California Edison Company. The plant is unusual in its fuel choice and utilization. The fuel includes both wood chips and a variety of waste agricultural materials. These are processed and blended to provide a stable fuel product for the boiler. a recirculating fluidized bed boiler is used. The use of agricultural waste for fuel provides several benefits. Local truckers benefit by an added need for services. The plant itself, of course, provides employment opportunities and locally-generated electrical power

  4. Marine nuclear power plant simulator

    International Nuclear Information System (INIS)

    In this paper, a real time simulator of nuclear power plant for ship propulsion is described. The simulator is composed of a hybrid computer and an operating console. Simulated power plant is a 36 MWt PWR plant. Reactor kinetics, fuel temperature, primary coolant temperature, primary pressure, temperature and pressure of steam in the steam generator, steam flow, rotating speed of the propeller shaft, and various controlling system are simulated. Using this simulator, frequency response functions of the reactor power to the variation of reactivity and load were measured. (author)

  5. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    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

  6. 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.

  7. Owners of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Reid, R.L.

    2000-01-12

    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 November 1999. The report is divided into sections representing different aspects of nuclear plant ownership.

  8. Periodic safety reviews of nuclear power plants

    International Nuclear Information System (INIS)

    Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

  9. Space nuclear reactor power plants

    International Nuclear Information System (INIS)

    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

  10. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    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.)

  11. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

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

  12. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    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.)

  13. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    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)

  14. Nuclear power plant

    International Nuclear Information System (INIS)

    The present invention provides reduction of volumes of buildings and the area of the buildings having a plurality of plants. Namely, a plurality of reactor building areas corresponding to a plurality of plants are disposed in a reactor building. In each of the reactor building areas, apparatuses including reactors of the plants are disposed. In addition, a plurality of reactor wells, spent fuel pools, pools for temporary storing facilities are arranged on an identical line. With such a constitution, since various kinds of facilities in the reactor buildings can be used in common, the volume of buildings and areas for the buildings in the plants as a whole can be reduced. In addition, turbine buildings can be used in common by the same idea. As a result, the number of buildings, the volume of the buildings and the area of the buildings of the plants can be reduced as a whole thereby enabling to reduce the steps, costs and materials required for building construction. (I.S.)

  15. Experiences on ISO-14001 certification of nuclear power plants

    International Nuclear Information System (INIS)

    In order to minimize the environmental impact from developmental activities, nuclear industry has played a leading role in evolving proper and effective environmental management practices right from inception. A comprehensive radiation protection policy has been evolved for nuclear energy development. The unique design concepts of Indian Nuclear Power Plants i.e. Pressurized Heavy Water Reactors (PHWRs), offer certain intrinsic advantages with respect to safety both during normal operation and accident conditions. In addition, in the engineering design of nuclear power plant, safety is further enhanced considerably by providing double back-upped engineered safety systems. Recently, Nuclear Power Corporation of India [NPCIL] has taken a drive to develop and implement Environmental Management System (EMS) to all its operating stations in line with ISO-14001 standards and certification by the accredited agencies. In this respect EMS of Narora Atomic Power Station (NAPS), Kakrapar Atomic Power Station (KAPS), Tarapur Atomic Power Station (TAPS), Madras Atomic Power Station (MAPS) and Rajasthan Atomic Power Station (RAPS 1 and 2) are certified for ISO-14001 by an accredited agency. Schedules have been worked out for the remaining atomic power stations too. The present paper is an attempt to highlight the experiences gained during the process of EMS implementation and certification as per ISO-14001 for nuclear power plants in India. (author)

  16. Operate a Nuclear Power Plant.

    Science.gov (United States)

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  17. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides detailed guidance on the provisions of the Code on the Safety in Nuclear Power Plants: Operation, IAEA Safety Series No. 50-C-O(Rev.1) on the maintenance of structures, systems and components. Like the Code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing Codes and Safety Guides relating to nuclear power plants. Effective maintenance is essential for safe operation of a nuclear power plant. It not only ensures that the level of reliability and effectiveness of all plant structures, systems and components having a bearing on safety remains in accordance with design assumptions and intent, but also that the safety status of the plant is not adversely affected after commencement of operation. Nuclear power plant maintenance requires special attention because of: Limitations set by requirements that a minimum number of components remain operable even when the plant is shut down in order to ensure that all necessary safety functions are guaranteed; Difficulty of access to some plant items even when the plant is shut down, due to radiation protection constraints; Potential radiological hazards to site personnel and the public. This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, selecting and training maintenance personnel, providing maintenance facilities and equipment, procuring stores and spare parts, reviewing, controlling and carrying out plant modifications, and generating, collecting and retaining maintenance records for establishing and

  18. Atomic power generation and future technical progress

    International Nuclear Information System (INIS)

    The construction of the world's first atomic power station in the Soviet Union in 1954 not only marked the beginning of a new trend in power engineering but also clearly demonstrated the practicability of human utilization of the vast resource of nuclear energy. The discovery of the fundamental possibility of using the energy released by the chain reactions associated with fission of heavy nuclei and fusion of light nuclei was a stupendous gift of science. The full significance of these revelations will appear later, at the end of this century, but it is already clear that the widespread use of nuclear energy from fission and fusion is inevitable, as the only technically and economically satisfactory way of overcoming the shortage of cheap fuels such as oil and gas. The large-scale development of atomic power engineering for various purposes - electric power, process heat and district heating, heat and power supplies for the metallurgical industry, power and heat for different branches of the chemical industry and radiation stimulation of chemical products - will help to save oil and gas so that they can be used for purposes where they are most difficult to replace

  19. Wind power plant system services

    DEFF Research Database (Denmark)

    Basit, Abdul; Altin, Müfit

    modern power system with large scale integration wind power. This study presents the investigation of the real-time balance control in a modern Danish power system, where WPPs can actively contribute to active power balance control. New solutions for the automatic generation control (AGC) dealing with...... WPPs are developed and analysed. The main results of this research work show that the WPPs can actively contribute to power balance control through primary and secondary response. The integration of WPPs control into the AGC is of high relevance, particularly in situations when wind power is...... 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, in a...

  20. Decommissioning, safe enclosure, and dismantling licensing for nuclear power plants according to section 7 subsection 3 of the Atomic Energy Act

    International Nuclear Information System (INIS)

    The contribution is concerned from a legal point of view with the systematic recording, classification and assessment of specific problems concerning the post-operational phase of a nuclear power plant. As an introduction, present experience with decommissioning in the Federal Republic of Germany is dealt with. The first part treats the factual side of section 7 III AtG, explains the terms mentioned, the concrete extent of licensing and priority relations. In part 2 the preconditions for licensing pursuant to section 7 III AtG are dealt with, the stipulations of which are made difficult in particular on account of the reference in section 7 III sentence 2 AtG. The third part is concerned with the legal consequence of section III AtG, i.e. the extent of official discretionary powers, whereby aspects of radioactive waste management carry great weight. In part four administrative and procedural particularities in the legal sense relating to licensing according to section III AtG are discussed. (orig./HP)

  1. Artificial intelligence in nuclear power plants

    International Nuclear Information System (INIS)

    The IAEA Specialists' Meeting on Artificial Intelligence in Nuclear Power Plants was arranged in Helsink/Vantaa, Finland, on October 10-12, 1989, under auspices of the International Working Group of Nuclear Power Plant Control and Instrumentation of the International Atomic Energy Agency (IAEA/IWG NPPCI). Technical Research Centre of Finland together with Imatran Voima Oy and Teollisuuden Voima Oy answered for the practical arrangements of the meeting. 105 participants from 17 countries and 2 international organizations took part in the meeting and 58 papers were submitted for presentation. These papers gave a comprehensive picture of the recent status and further trends in applying the rapidly developing techniques of artificial intelligence and expert systems to improve the quality and safety in designing and using of nuclear power worldwide

  2. Seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on 'Benchmark study for the seismic analysis and testing of WWER type nuclear power plants'. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

  3. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

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

  4. Energy sources and power plants

    International Nuclear Information System (INIS)

    Energy is obtained from various energy sources (coal, petroleum, natural gas, nuclear fuels, wind energy, solar energy, hydro power, biomass, geothermal energy). These differ in each case with respect to their availability, methods of their production and the required power plant technologies. As technologies of the future fuel cells and nuclear fusion are traded.

  5. Assessment of gamma emitting radionuclides in the aquatic ecosystem of Kakrapar Atomic Power Station and evaluation of radiological doses to aquatic plants

    International Nuclear Information System (INIS)

    During operation and maintenance of Pressurised Heavy Water Reactors (PHWRs) at Kakrapar Atomic Power Station (KAPS), low level radioactive liquid waste is generated and released to the aquatic ecosystem (Moticher lake). The silt and aquatic weed (Hydrilla verticillata) samples collected from different locations in Moticher lake were analysed for 137Cs, 134Cs, 65Zn, 60Co, 54Mn and 40K during 2007-2008. A wide variation in activity levels of 137Cs, 134Cs, 65Zn, 60Co, 54Mn and 40K in silt and weed samples were observed in aquatic system of KAPS. The activity buildup in the silt is confined to a small area in the Moticher lake. The activity levels were found to be insignificant at 1 km away from discharge point (upstream and downstream). An attempt was made to evaluate the radiological dose to aquatic weed (Hydrilla verticillata), which was found to be well within the dose limit prescribed by US DOE. The total radiological dose due to the naturally occurring radionuclide (40K) is comparatively higher than that of other reactor released gamma emitting radionuclides. (author)

  6. TVA's nuclear power plant experience

    International Nuclear Information System (INIS)

    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

  7. Nuclear power plant

    International Nuclear Information System (INIS)

    A modular design for an internal heat exchanger for a power reactor with separate primary and secondary cooling circuits, eg. a PWR, is described. The purpose of the design is to reduce the thermal stresses in the feed water system by a special arrangement of this. (JIW)

  8. Baseline for coal powered plants

    International Nuclear Information System (INIS)

    Frequently, the cost performance of a specific power plant is measured by comparing the cost with the statistical average cost of plants through the industry. Unless all of the variables have been considered, this comparison may draw a misleading conclusion. The capital cost of a power plant varies with time (year of commercial operation and construction duration) due to the effect of inflation. Examine these cost data in detail revels that the variation in the cost is very wide. For example, published data shows that the ratio between the highest to the lowest cost per KW is more than 4 to 1 for the plants that commenced operation in 1984. The wide variation of the capital costs is explained below in relation to various influencing factors, differing conditions, and scope of work. This paper provides a defined baseline coal-fired plant, an analysis of its capital costs, and a discussion of the reasons for such wide variation

  9. Providing emergency supply of nuclear power plants

    OpenAIRE

    ROZMILER, Jiří

    2013-01-01

    Work "Providing emergency power nuclear power plant" describes how solving their own consumption nuclear power plant, as emergency power supply is designed and how it should be a solution of known states of emergency, having an immediate impact on the power consumption of their own nuclear power plants. The aim of this thesis is to propose options to strengthen its own emergency power consumption of nuclear power plants, one might say-more resistant to harsh extremes, which could lead to loss...

  10. Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

    International Nuclear Information System (INIS)

    After 20 years of commercial operation, the Connecticut Yankee Atomic Power Station decided to replace the original nuclear instrument system. The plant was motivated primarily by reliability and maintainability problems, the former attributed to equipment wearout and discrete component failure, and the latter to the unavailability of qualified spare parts, another effect of the equipment's age. In replacing the system, the plant also had to address current regulatory, design, and plant technical specification requirements, including physical separation, signal isolation, and changes in equipment qualification. This paper discusses the motivation for the system's replacement, the challenges to the plant engineers and equipment designers, the ways in which the new design met the challenges, the test results of the new system, and other potential benefits supported by the test results

  11. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To provide a ballast tank, and nuclear power facilities within the containment shell of a pressure resistance structure and a maintenance operator's entrance and a transmission cable cut-off device at the outer part of the containment shell, whereby after the construction, the shell is towed, and installed by self-submerging, and it can be refloated for repairs by its own strength. Constitution: Within a containment shell having a ballast tank and a pressure resisting structure, there are provided nuclear power facilities including a nuclear power generating chamber, a maintenance operator's living room and the like. Furthermore, a maintenance operator's entrance and exit device and a transmission cable cut-off device are provided within the shell, whereby when it is towed to a predetermined a area after the construction, it submerges by its own strength and when any repair inspection is necessary, it can float up by its own strength, and can be towed to a repair dock or the like. (Yoshihara, H.)

  12. Chemistry in power plants 2011

    International Nuclear Information System (INIS)

    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

  13. Nuclear power plant

    International Nuclear Information System (INIS)

    The plant of the present invention can suppress the amount of clad in feedwater when drains of a moisture content separation heater or a high pressure feedwater heater are recovered. That is, the moisture content separation heater has ferrite or austenite type stainless steel heat transfer pipes. A chromium-enriched layer is formed on the surface of the heat transfer pipe by chromizing treatment or flame spraying. Then, a stainless steel heat transfer pipe having chromium-enriched layer is incorporated to at least one of the moisture content separation heater or the high pressure feedwater heater. During plant operation, the temperature of heated steams is as high as 235 to 282degC. Accordingly, this is a severe corrosion region for ferrite or austenite stainless steel. However, the chromium-enriched layer of excellent corrosion resistance is formed on the surface of the heat transfer pipe. Accordingly, metal ingredients are less leached. As a result, even if the drains are recovered to feedwater, increase of concentration of the clads in the feedwater can be prevented. (I.S.)

  14. 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...

  15. Financing solar thermal power plants

    International Nuclear Information System (INIS)

    The commercialization of concentrating solar power technology took a major step forward in the mid 1980s and early 1990s with the development of the SEGS plants in California. Over the years they have proven that parabolic trough power technologies are the most cost-effective approach for commercial scale solar power generation in the sunbelt countries of the world. However, the question must be asked why no additional solar power plants have been built following the bankruptcy of the developer of the SEGS projects, LUZ International Limited. Although many believe the SEGS projects were a success as a result of parabolic trough technology they employ, in truth, the SEGS projects were developed simply because they represented an attractive opportunity for investors. Simply states, no additional projects have been developed because no one has been able to put together a similarly attractive financial package to potential investors. More than $1.2 billion in private capital was raised in debt and equity financing for the nine SEGS plants. Investors and bankers who make these investments are the real clients for solar power technologies. They are not interested in annual solar to electric efficiencies, but in risk, return on investments, and coverage ratios. This paper will take a look at solar power projects form the financier's perspective. The challenge in moving forward is to attract private investors, commercial lenders, and international development agencies and to find innovative solutions to the difficult issues that investment in the global power market poses for solar power technologies

  16. Financing Solar Thermal Power Plants

    International Nuclear Information System (INIS)

    The commercialization of concentrating solar power technology took a major step forward in the mid 1980s and early 1990s with the development of the SEGS plants in California. Over the years they have proven that parabolic trough power technologies are the most cost-effective approach for commercial scale solar power generation in the sunbelt countries of the world. However, the question must be asked why no additional solar power plants have been build following the bankruptcy of the developer of the SEGS projects, LUZ International Limited. Although many believe the SEGS projects were a success as a result of parabolic trough technology they employ, in truth, the SEGS projects were developed simply because they represented an attractive opportunity for investors. Simply stated, no additional projects have been developed because no one has been able to put together a similarly attractive financial package to potential investors. More than $1.2 billion in private capital was raised in debt and equity financing for the nine SEGS plants. Investors and bankers who make these investments are the real clients for solar power technologies. They are not interested in annual solar to electric efficiencies, but in risk, return on investments, and coverage ratios. This paper will take a look at solar power projects from the financier's perspective. The challenge in moving forward is to attract private investors, commercial lenders, and international development agencies and to find innovative solutions to the difficult issues that investment in the global power market poses for solar power technologies

  17. Pressurised fluidised bed power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jansson, S.A.; Anderson, L. [ABB Carbon AB, Finspong (Sweden)

    1997-12-31

    The combined experience from almost 75,000 hours of operation on widely different coals in Pressurised Fluidised bed Combined-cycle (PFBC) plants in Sweden, Spain, the US and Japan have demonstrated the viability of ABB`s PFBC technology and the general simplicity of the concept, as well as plant control principles and serviceability. This technology is now commercially offered world-wide and PFBC is being recognized as a competitive solution for power and for combined heat and power applications. The combined-cycle feature makes PFBC highly efficient for power generation. When compared with conventional power plants, and for the same steam conditions, a PFBC plant typically produces at least 10% more electricity from the same amount of coal. There is potential for future additional efficiency increases. The coals used so far in the existing PFBC power plants include bituminous coals with a wide range of sulphur and ash contents, and a sub-bituminous Spanish `black lignite` with extremely high and variable levels of sulphur, ash, and moisture. Brown coal from the eastern parts of Germany will be used as the fuel in a newly ordered PFBC plant in Cottbus, Germany. Oil shale, petcoke, anthracite, and different types of biomass mixed with coal are presently being considered for other PFBC projects under discussion. PFBC is suitable for greenfield plants, but a market also exists for PFBC repowering of older steam plants. Repowering provides an opportunity to convert older, low capacity factor units into assets that lower the system`s production costs as well as improving environmental performance. Ash utilisation also holds promise, elevating the ash from a disposable waste to a valuable resource. 6 refs., 3 figs., 1 tab.

  18. Atomic thermoelectric power stations of small capacity

    International Nuclear Information System (INIS)

    In the beginning of 90 years a competition among atomic power stations of small capacity 'ATPS SC-91' was conducted under the aegis of Russian Nuclear Society. More than 20 designs of atomic power stations of small capacity (ATPS SC) were presented at the competition by way of conversion developments of leading design and planning organizations of Russian Minatom. The preliminary analysis of ATPS SC showed their high competitiveness comparing to traditional power-suppliers in the remote Russian territories even if there were local energy resources. In Russia by order of 'Rosenergoatom' Concern the ATPS SC project is developed on the basis of a floating power unit (FPU) with KLT-40S RF.The stationary option of ATPS SC with KLT-40S RF was developed for the Republic of Kazakhstan.The options of the project optimization made afterwards by NNC RK specialists allowed to substantially reduce construction budget due to, first, the change of price policy, and, secondly, the use of a number of supporting buildings, structures and systems located on the prospective construction sites. In Russia the designs of floating ATPS SC are developed, at first, on the basis of ABV-6 reactor facilities

  19. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To prevent liquid wastes from being discharged out of the system by processing to recover them in the nuclear reactor and reusing them. Constitution: Discharge of liquid wastes to the surrounding atmosphere are completely eliminated by collecting floor drains, a part of processing water for the regeneration of liquid wastes, non-radioactive steam drains and laundry drains conventionally discharged so far out of the system, processing them in a concentrator, a desalter or the like into water of a high purity and extremely low radioactive concentration, storing the water in an exclusive storage tank and supplying it as a steam or supplementing water to each portion in the plant that requires water of such high purity and extremely low radioactivity. (Yoshihara, H.)

  20. Thermal power plants and environment

    International Nuclear Information System (INIS)

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

  1. Ocean power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dembicki, E.

    1982-01-01

    In the fall of 1980 on the shores of the Hawaiian Islands, a floating laboratory of the United States was successfully introduced for testing a heat exchanger and pipes for collecting cold water of the OTES with power of 1 MW. The first American OTES N=10-40 MW should start operation in 1985. By the year 2000, ..sigma..N of the U.S. OTES should reach 10 GW. The Japanese OTES N=10-25 MW should start up in 1989. The experimental OTES N=100 KW has been in operation since October 1981 on the Nauru Island. An OTES of 2 MW is under construction. The concern Empain-Schneider is involved in planning the OTES of closed cycle in France, and the concern CGE is planning the OTES of open cycle.

  2. Temperature Effect to Solar Power Plant

    OpenAIRE

    Modestas Pikutis

    2015-01-01

    There are a lot of different efficiency photovoltaic cells, which are used in solar power plants. All of these different photovoltaic cells are affected by different environment conditions. Maximum power point tracking is the main way to increase solar power plant efficiency. Mostly systems of maximum power point tracking are slow or inaccurate, that means the system cannot stay in maximum power point in solar power plant. This is the main reason why mostly of solar power plants are working n...

  3. Nuclear power plant

    International Nuclear Information System (INIS)

    In a condensate cleanup system and a reactor water cleanup system of a BWR-type reactor, in which primary coolants flow, there is disposed a filtering and desalting device using hollow thread membrane filter and ion exchange resin for a condensate cleanup system, and using a high temperature filter made of a metal, a metal oxide or ceramics as a filtering material and a precoat filter made of a powdery ion exchange resin as a filtering material for a reactor water cleanup system. This can completely remove cruds generated in the condensate system. Since the reactor water cleanup system comprises the powdery resin precoat-type filtering and desalting device and the high temperature filter using ceramics, ionic impurities such as radioactive materials can be removed. Accordingly, cruds are not carried into the inside of the reactor, and since the radioactive concentration in the reactor water is reduced, radiation exposure upon periodical inspection can be minimized almost to zero, to attain a clean plant. (T.M.)

  4. Packing solutions for power plants

    International Nuclear Information System (INIS)

    Asbestos packings are being replaced in more and more countries with alternative products. This paper discusses modern packing solutions for valves and pumps in power plants. Die-moulded packing rings made of expanded graphite foil are described m detail, with recommendations for correct installation. Application examples for spring-loaded valves and cover lid seals are given. As an alternative for repair and service use, a braided expanded graphite packing reinforced with Inconel wire is described. Proposals for sealing various pump applications in power plants are also made. (Author)

  5. Mental models and learning from experience in nuclear power plants

    International Nuclear Information System (INIS)

    This paper proposes that the improvement of plant functioning and the enhancement of safe performance depend greatly on the ability to interpret experience from within and outside the plant: Plants are learning organizations. The management of risk thus involves learning to identify and reduce entry into precursor situations and to recover rapidly from deficiencies. Various learning mechanisms exist that analyze plant incidents and disseminate this information inside plants, across plants, and worldwide, including, for example, various Institute of Nuclear Power Operations and International Atomic Energy Agency programs. Underlying these learning processes are plant employees' own understanding and interpretation of operational experience

  6. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

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

  7. Nuclear power plant life extension

    International Nuclear Information System (INIS)

    Current licensing emphasis is different from that existing when older nuclear power plants received their operating licenses. Today, there is increased regulatory focus on utility performance measured through new inspections such as the safety system functional inspection and the safety systems outage modifications inspection; and the use of performance indicators. These programs are intended to identify poorer performing plants and concentrate on improving overall plant performance. This paper discusses how, in an attempt to improve the maintenance performance of the nuclear industry, the U.S. Nuclear Regulatory Commission recently began work on a maintenance rule. In addition, the NRC will require partial probabilistic risk evaluations for each plant that will provide new insights as to a plant's risk. Risk information is being used to prioritize inspections

  8. Solar thermionic power plant. II

    Science.gov (United States)

    Abou-Elfotouh, F.; Almassary, M.; Fatmi, H.

    It has been shown that the geometric configuration of a central receiver solar electric power plant SEPP can be optimized for the high power density and concentration required for the operation of a thermionic converter. The working period of a TDC constructed on the top of a SEPP in Riyadh area is 5 to 6 hours per day in winter and 6 to 8 hours in summer. At the 25 percent conversion efficiency achieved by a laboratory test model, a reduction in the cost per unit power of 8-12 per cent is expected. The spectral behavior and work functions of the working surface of the thermionic electrodes were investigated

  9. Noise from wind power plants

    International Nuclear Information System (INIS)

    First, the generation of noise at wind power plants and the character of the sound is described. The propagation of the sound and its dependence on the structure of the ground and on wind and temperature is treated next. Models for calculation of the noise emission are reviewed and examples of applications are given. Different means for reducing the disturbances are described

  10. Fire protection in power plants

    International Nuclear Information System (INIS)

    Graphex-CK 23 is a unique sodium fire extinction product. Minimum amounts of powder are required for very fast action. The sodium can be put to use again, when the fire has been extinguished. It can be applied in other industrial branches and with other metals, e.g. sodium/potassium circuits or lithium coolant in power plants.

  11. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    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)

  12. World nuclear power plant capacity

    International Nuclear Information System (INIS)

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

  13. Environmental impact of nuclear power plant

    International Nuclear Information System (INIS)

    The environment, is radioactive, by reason of reception of rays of sky and earth, atoms on body and normal activities(fossil fuel). Activities on fossil fuel cycle, led to environmental pollutions. Also, the aim of this research is survey of environmental impact of nuclear power plant and determination management and monitoring policies. The result of this research showed that in the fossil fuel cycle (exploration, extraction, mill), produced different level radioactive wastes (low, middle, high), chemical material, heat, oily material and wastewater, that by use of radioactive waste management, destructive effect of pollutant can be decreased

  14. Financing Solar Thermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Price, H. W.; Kistner, R.

    1999-11-01

    The commercialization of concentrating solar power technology took a major step forward in the mid 1980s and early 1990s with the development of the SEGS plants in California. Over the years they have proven that parabolic trough power technologies are the most cost-effective approach for commercial scale solar power generation in the sunbelt countries of the world. However, the question must be asked why no additional solar power plants have been build following the bankruptcy of the developer of the SEGS projects, LUZ International Limited. Although many believe the SEGS projects were a success as a result of parabolic trough technology they employ, in truth, the SEGS projects were developed simply because they represented an attractive opportunity for investors. Simply stated, no additional projects have been developed because no one has been able to put together a similarly attractive financial package to potential investors. More than $1.2 billion in private capital was raised i n debt and equity financing for the nine SEGS plants. Investors and bankers who make these investments are the real clients for solar power technologies. They are not interested in annual solar to electric efficiencies, but in risk, return on investments, and coverage ratios. This paper will take a look at solar power projects from the financier's perspective. The challenge in moving forward is to attract private investors, commercial lenders, and international development agencies and to find innovative solutions to the difficult issues that investment in the global power market poses for solar power technologies.

  15. Environmental gamma radiation monitoring around Tarapur Atomic Power Station

    International Nuclear Information System (INIS)

    Tarapur Atomic Power Station (T.A.P.S.) is located on the Arabian Sea coast and uses enriched uranium as fuel and seawater as condenser coolant. It is India's first nuclear power plant. It was initially constructed with two boiling water reactor (BWR) units of 210 MWe each. The capacity of units 1 and 2 was reduced to 160 MWe later on due to technical difficulties. Units 1 and 2 were brought online for commercial operation on October 28, 1969. Two Pressurised Heavy Water Reactor (PHWR) (units 3 and 4) of 540 MW each was brought online for commercial operation on August 18, 2006 and September 12, 2005 respectively. The Power Reactor Fuel Reprocessing Plant (PREFRE), which was commissioned in 1976, is located about 1.3 Km East of TAPS. Presently, Tarapur is a multifacility site. In addition to TAPS and PREFRE, Waste Immobilization Plant (WIP), Advanced Fuel Fabrication Facility (A3F), Away from Reactor (APR) fuel storage facility and Tarapur Radwaste treatment plant (TRAP) are operating at the site. At TAPS, gaseous effluents are discharged through 110 m stack to atmosphere. The results of environmental gamma monitoring programme carried out at the taps sites in terms of annual average dose to public is given in this paper

  16. Conception and design of steam power plants

    International Nuclear Information System (INIS)

    The manual presents the fundamentals of thermodynamics and fluid mechanics, the main components of steam power plants, and the power generation process. The following concepts and subjects are discussed at length: steam generator; steam turbines; turbogenerators; condensers; cooling technology; water/steam cycle and water treatment; design data of fossil-fuelled power plants; design and optimisation of nuclear power plant thermodynamics; pipelines and fittings; control systems in steam power plants; connection to the electricity grid and self-supply of thermal power plants; power plant transformer concepts and definitions. (HAG)

  17. Life extension of German nuclear power plants only with the consent of the Federal Council? The importance and extent of the need for consent to an amendment to the German Atomic Energy Act

    International Nuclear Information System (INIS)

    In its coalition agreement of October 26, 2009, the new German federal government plans ''to extend the service life of German nuclear power plants while, at the same time, complying with the strict German and international safety standards.'' This has triggered a debate not only about (nuclear) energy, as in the past election campaign in the summer of 2009, but also about the constitutional law issue whether an amendment to the Atomic Energy Act resulting in longer operating life of nuclear power plants required the consent of the Federal Council (the ''Bundesrat,'' the second chamber of parliament). After the election to the state parliament in North Rhine-Westphalia on May 9, 2010, majority in the Federal Council changed. As a consequence, no consent to an amendment to the Atomic Energy Act must be expected. In view of the large number of recent statements about constitutional law in opinions for various federal and ministerial accounts as well as firms and associations, the outline by R. Scholz in the May issue of atw 2010 will be followed in this issue by the key points of examination of the need for consent, under aspects of constitutional law, and an attempt will be made to explain the evaluations underlying the generation of a legal concept about these items. The decision by the German Federal Constitutional Court of May 4, 2010, published on June 11, 2010, plays a major role in this respect because it established clarity in some important aspects of a legal subject matter in the field of state admini-stration on behalf of the federation, albeit in the field of air traffic law, not nuclear law. However, the structures of the norms in the German Basic Law (Art. 87c and Art. 87d, para.2) to be applied are almost identical. The energy policy and energy economy aspects of a plant life extension are considered along with the option of an appeal to the Federal Constitutional Court against any plant life extension. Finally, the key findings are summarized briefly

  18. Safety for nuclear power plants

    International Nuclear Information System (INIS)

    The September 11, 2001 terrorist attacks on the World Trade Center in New York have reopened the debate in Germany abut the safety of existing nuclear power plants. On the one hand, it culminated in the demand, made from a prominent political position, to disconnect from the grid prematurely five of the older nuclear power plants because they offered no sufficient protection from terrorist attacks carried out by means of commercial airliners. On the other hand, the competent German Federal Ministry of the Interior to this day has not been able to detect a hazardous situation for Germany which would require nuclear power plants (or other facilities) to be shut down - temporarily -so as to reduce their hazard potential. The legal situation is discussed in detail. It is evident that the debate about the safety of any kind of industrial plants will go on and will be revived by any kind of event. Despite the growing need for public safety, it must not be overlooked in the public debate that an absolute exclusion of risk is impossible and that, consequently, there can be no absolute protection of any legal object. (orig.)

  19. Environmental monitoring around nuclear power plant sites

    International Nuclear Information System (INIS)

    The environmental monitoring around nuclear power plant sites is presented. The basic policy that no part of the ecosystem should be subjected to excessive (above natural) radiation exposure is realized by predictive methodology of environmental and dosimetric models. The validation of these models is achieved through environmental monitoring around nuclear power plant sites right from the pre-operational period through operational phase. The 'potential contaminated media' are monitored in pre-operational phase. The measurements carried out in the environmental matrices for assessment of the impact on the population demonstrate that the objectives of the Department of Atomic Energy are fully realized. These activities are carried out at each nuclear power plant site by establishing an Environmental Survey Laboratory, which operates under the administrative and technical control of the Health Physics Division of BARC. This arrangement ensures independence from the operating organisation and better public acceptance of data generated. The results of environmental monitoring indicate that the radiation dose received by members of the public is well below the regulatory limits. (author)

  20. Optimization of Maputo Power Plant

    OpenAIRE

    Abacar, Armando

    2013-01-01

    The Electricidade de Moçambique, E.P. (EDM) is the power utility in Mozambique, responsible to generate, transport and distribute electricity all over the country. The company has three gas turbines installed at Maputo Power Plant. All units burn diesel oil and are used only for back up. Currently only the unit #2 is available for operation. The main constraint that EDM faces is the high operation costs due to diesel price. Hence the company is considering converting units #2 and #3 to burn n...

  1. Present situation of floating nuclear power plants

    International Nuclear Information System (INIS)

    The present situation of investigation and the future problems of floating nuclear power plants in Japan are examined, referring to those in USA. The committee report on a new power generation system in 1970 is quoted. In this report, the site conditions are supposed to be 5 km offshore, 100m water depth, 60 m/sec wind velocity, 10 m wave height, 200 m wave length, 12 seconds wave period 0.2 g earthquake acceleration, and 2.5 knots tide current. The semisubmersible hull of double construction 15 m under water is employed. A pair of 1,000,000 kW BWR reactors are utilized. A sea water desalting unit using bleed steam from turbines is installed. The solid radioactive wastes packed in drums are disposed in sea. The design and cost estimation were made. The names of the organizations who have made investigation in this field, namely the Civil Engineering Society, the Sience and Technology Agency and other several centers, are reported. The Chubu Electric Power Company is forwarding its project. Referring to the investigations in USA, the project of Atlantic nuclear power station unit is described. A report of plant design has been submitted by O.P.S. to United States Atomic Energy Commission in 1973. The Coastal Area Facilities Act was instituted in New Jersey in 1973. Although the Atlantic nuclear power station has been postponed, it is the most feasible project. For the realization of a floating nuclear power plant in Japan, investigation must be started on the ground construction that can endure the construction of breakwater in water depth of 14 to 30 meter. (Iwakiri, K.)

  2. An Embalse nuclear power plant basic principles simulator

    International Nuclear Information System (INIS)

    A nuclear power plant basic principles simulator is a package of programs that numerically solve the dynamic equations of the simulated plant. This kind of tools is mainly used in the first step of training of operational personnel, to allow mental representation of physical phenomena governing the plant. They are also used for students or professional training, and experienced operators can also improve there performance under abnormal operation situations using the simulator. For the Embalse nuclear power plant, mainly the thermohydraulic behaviour, is simulated. The mathematical model was adapted from MANUVR, a code developed at the Electric Systems and Control Department of the National Atomic Energy Commission (CNEA). (Author)

  3. Nuclear power plants and environment

    International Nuclear Information System (INIS)

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

  4. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    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.)

  5. Tidal Power Plant Energy Estimation

    Directory of Open Access Journals (Sweden)

    Silva–Casarín R.

    2010-04-01

    Full Text Available In this paper a methodology is presented which allows a quick and simple means of estimating the potential energy that can be obtained from a tidal power plant. The evaluation is made using a normalised nomograph, which is a function of the area of the tidal basin against the electricity installed capacity to thus obtain the potential energy for any location. The results describe two means of operation, one of "flow tide" and the other "flow–ebb tides", with two tidal basin systems operating: single and double reservoir systems. To obtain the normalised nomograph the numerical results for simulations of several tidal power plants under differing operational conditions over a period of one year. These conditions were established by varying the electricity installed capacity, the hydraulic conditions in "flow tide", "ebb tides" or both and with single or double reservoir systems and using sea level information taken every 15 minutes. To validate the model information from the tidal power plant at Rance, France, was used, which includes data concerning production, electricity installed capacity, turbine characteristics and tidal ranges. A very good correlation was found between the results of the numerical model and those reported in various technical reports.

  6. On the setting change of scaling factors for the homogeneous solidified wastes from Tsuruga Plant I of Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Following a request from business operator for confirmation of the generated wastes and their point of view, necessary observation data and required information, JNES (Japan Nuclear Energy Safety Organization) examined the adaptability to the guidelines and regulations of the proposal for changing the scaling factors of Strontium 90 in the homogeneous solidified wastes (concentrated effluent solidified with asphalt) generated from Tsuruga Plant I during 2004-2005. The availability of the proposal is agreed in this report. (S. Ohno)

  7. Financing nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Much is at stake in developing a financial strategy for decommissioning nuclear power plants. Since decommissioning experience is limited to relatively small reactors, will the costs associated with larger reactors be significantly higher. Certainly the decommissioning issue intersects with other critical issues that will help to determine the future of commercial nuclear power in the US. The author examines briefly the basic concepts and terms related to decommissioning expenses, namely: (1) segregated fund; (2) non-segregated fund; (3) external method; and (4) internal method. He concludes that state regulatory commissions have turned increasingly to the external funding method because of increasing costs and related problems associated with nuclear power, changing conditions and uncertainties concerned with utility restructuring, and recent changes in federal tax laws related to decommissioning. Further, this trend is likely to continue if financial assurance remains a primary concern of regulators to protect this public interest

  8. Nuclear power plant computer replacement

    International Nuclear Information System (INIS)

    Consumers Power Company (CPCo) has recently completed an ambitious project to replace the non-safety-related plant process computer for the Palisades Nuclear Plant. The replacement computer retains the functions of the old plant computer system with minor exceptions. However, the architecture of the new computer system is vastly improved from the old plant computer. The hardware and software components of the new computer system are the state of the art. The old system consisted of five stand-alone computers, each performing their intended function separately. The new architecture employs a number of computing and data acquisition nodes networked together to gather, share, process, present, and store data more efficiently. For cost efficiency, some of the old hardware, such as the Critical Functions Monitoring System multiplexer, has been retained. The new computer system has a significantly higher availability, and lower maintenance cost. It performs certain functions that were not possible with the old system, such as real-time validation of rod position monitored by the Plant Information Processor and the Secondary Position Indicator. While the new computer system is more capable, more reliable, more user friendly, and easier to maintain, taking it to operability status presented CPCo with some new and challenging issues

  9. Robots for nuclear power plants

    International Nuclear Information System (INIS)

    In many industrial applications of robots, the objective is to replace human workers with machines that are more productive, efficient, and accurate. But for nuclear applications, the objective is not so much to replace workers as it is to extend their presence - for example, to project their reach into areas of a nuclear plant where the thermal or radiation environment prohibits or limits a human presence. The economic motivation to use robots for nuclear plant inspection and maintenance is centered on their potential for improving plant availability; a by-product is the potential for reducing the occupational radiation exposure of plant personnel. Robotic equipment in nuclear applications may be divided into two broad categories: single-purpose devices with limited ability to perform different operations, and reprogrammable, multi-purpose robots with some degree of computer-based artificial intelligence. Preliminary assessments of the potential for applying robotics in nuclear power plants - mainly at surveillance and inspection tasks - have been carried out. Future developments are considered

  10. Maintenance experience at Rajasthan atomic power station

    International Nuclear Information System (INIS)

    The Rajasthan Atomic Power Station is a twin-unit station of the CANDU-PHW type with a nominal rating of 200 MW(e) net per unit and on-power refuelling capability. Unit-I became critical in August 1972 and was declared commercial in December 1973. Unit-II is in an advanced stage of construction. Maintenance and repairs of both the nuclear and conventional equipment are done during routine planning, breakdown outages, poison shutdown outages and planned annual shutdown periods. Yearly, a period of three to four weeks may be needed for carrying out major inspection and maintenance activity on large equipment such as the steam turbine, generator, main condenser, station transformer, primary coolant recirculation pumps, moderator pumps and fuelling machines. Preventive maintenance jobs are planned and executed in accessible areas daily as a matter of routine and during poison shutdown outages in inaccessible areas. This requires that the maintenance crews be more or less continually on the alert. In addition to gamma radiation, radiation doses due to tritium are encountered and pose special problems for the maintenance personnel. During the past two years (1972-74) it was found that there is a need, in the maintenance crews, for more specialists for various radioactive and conventional jobs. This paper outlines the significant nuclear and conventional maintenance activities as well as problems in maintenance encountered during the period 1972-74. (author)

  11. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    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.)

  12. Atucha I nuclear power plant transients analysis

    International Nuclear Information System (INIS)

    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)

  13. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans

    International Nuclear Information System (INIS)

    This paper describes and evaluates five years of operation and test of the Shippingport Atomic Power Station and discusses the current technical developments and future plans of the Shippingport programme. This programme is directed towards development of the basic technology of light-water reactors to provide the basis for potential reduction in the costs of nuclear power. The Shippingport reactor plant has operated for over five years and has been found to integrate readily into a utility system either as a base load or peak load unit. Plant component performance has been reliable. There have been no problems in contamination or waste disposal. Access to primary coolant components for maintenance has been good, demonstrating the integrity of fuel elements. Each of the three refuelling operations performed since start-up of Shippingport has required successively less time to accomplish. Recently, the third seed was refuelled in 32 working days, about one quarter the time required for the first refuelling. The formal requirements of personnel training, written administrative procedures, power plant manuals, etc., which have been a vital factor in the successful implementation of the Shippingport programme, are described. The results obtained from the comprehensive test programme carried out at Shippingport are compared with calculations, and good agreement has been obtained. Reactor core performance, plant stability, and response to load changes, fuel element and control rod performance, long-term effects such as corrosion and radiation level build-up, component performance, etc., are discussed in this paper. The principal objective of the current and future programmes of the Shippingport Project in advancing the basic technology of water-cooled reactors is discussed. This programme includes the continued operation of the Shippingport plant, and the development, design, manufacture and test operation of a long-life, highpower density second core - Core 2. At its

  14. Environmental radionuclide concentrations in the vicinity of the Peach Bottom Atomic Power Station: 1991--1994

    International Nuclear Information System (INIS)

    The Maryland Power Plant Research Program monitors concentrations of natural, weapons, and power plant produced radionuclides in environmental samples collected from the Susquehanna River-Chesapeake Bay system in the vicinity of Peach Bottom Atomic Power Station (PBAPS). The purpose of this monitoring is to determine the fate, transport, and potential effects of power plant produced radionuclides. This report contains a description of monitoring activities and data collected during the period 1991 through 1994 and is the fifth in a series reporting monitoring results initiated at PBAPS in 1979

  15. Advanced Coordinating Control System for Power Plant

    Institute of Scientific and Technical Information of China (English)

    WU Peng; WEI Shuangying

    2006-01-01

    The coordinating control system is popular used in power plant. This paper describes the advanced coordinating control by control methods and optimal operation, introduces their principals and features by using the examples of power plant operation. It is wealthy for automation application in optimal power plant operation.

  16. New hydro power plant Dobsina III

    International Nuclear Information System (INIS)

    Another power plant will be added to the hydroelectric power plant Dobsina. Preparations for the construction of a small hydro power plant have started on the streams Hnilec and Dobsinsky Brook. Dobsina III will extend the portfolio of renewable sources of Slovenske elektrarne. (author)

  17. Occupational dose control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Reduction in occupational exposure at nuclear power plants is desirable not only in the interest of the health and safety of plant personnel, but also because it enhances the safety and reliability of the plants. This report summarises the current trends of doses to workers at nuclear power plants and the achievements and developments regarding methods for their reduction

  18. Nuclear power plant operating experience, 1976

    International Nuclear Information System (INIS)

    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

  19. Environmental studies and clearance compliance of Kudankulam Atomic Power Project

    International Nuclear Information System (INIS)

    Full text: Nuclear industry has played a leading role in evolving proper and effective environmental management impact from development practices right form inception thus minimizing the environmental impact from developmental activities of man. In the engineering design of nuclear power plant, safety is further enhanced considerably by providing double back-upped engineered safety systems. Besides the engineered safety, the other factors considered for ensuring environmental impact minimization are siting criteria, conservative rad-waste management, effluent treatment, application of stringent environmental protection standards for limiting waste discharges, an elaborate environmental surveillance program and an on site and off site emergency preparedness plan. Recently, nuclear power industry has taken a drive to develop and implement Environmental Management System (EMS) to all its operating stations in line with ISO-14001 standards. For Kudankulam atomic power project, a number of studies specifically for environmental protection are carried out to meet the requirements of Russian Federation, new guidelines of Ministry of environment and Forests (MOEF) and Atomic Energy Regulatory Board (AERB). In the present paper an attempt has been made to present the environmental management plan and clearance compliance status of the project

  20. Wind Power Plant Control - An Overview

    OpenAIRE

    Altin, Müfit; Teodorescu, Remus; Bak-Jensen, Birgitte; RODRIGUEZ, Pedro; Iov, Florin; Kjær, Philip C.

    2010-01-01

    Recent developments in wind turbine technology go towards installation of larger Wind Power Plants (WPPs). Therefore, power system operators have been challenged by the WPP penetration impacts in order to maintain reliabillity and stability of the power system. The revised grid codes have concentrated on the WPP connection point and as a result a WPP is considered as a single power plant. Nevertheless, compared to conventional power plants, WPPs have different inherent features such as conver...

  1. Small, moveable nuclear power plant

    International Nuclear Information System (INIS)

    Most reliable projections indicate that by the year 2000 approximately 25% of the world's electrical energy and possibly 10% of its process heat for industry will be provided by nuclear power plants. Whilst much of this will come from large nuclear steam raising units-in excess of 900 M.W.(e)-an increasing proportion will be provided from small modular plant, designed for portabiity or mobility. The technical, environmental and economic parameters of such a plant which will usually be of a size around 600 M.W.(e) or less and which in general terms derives its basic design features from nuclear marine propulsion units is reviewed. If suitably standardised, such a nuclear plant, mounted on barges, installed in ships or even airlifted into difficult locations, could provide an attractive solution to the energy problems of developing countries or remote communities. Apart from electrical energy production, the units could operate in a duplex mode to supply steam for central heating, sea-water or bore water distillation or industrial process heat. (Author)

  2. Power plant intake entrainment analysis

    International Nuclear Information System (INIS)

    Power plant condenser cooling water intake entrainment of fish eggs and larvae is becoming an issue in evaluating environmental impacts around the plants. Methods are required to evaluate intake entrainment on different types of water bodies. Presented in this paper is a derivation of the basic relationships for evaluating entrainment from the standing crop of fish eggs and larvae for different regions of a water body, and evaluating the rate of entrainment from the standing crop. These relationships are coupled with a 3D hydrodynamic and transport model that provides the currents and flows required to complete the entrainment evaluation. Case examples are presented for a simple river system, and for the more complex Delaware River Estuary with multiple intakes. Example evaluations are made for individual intakes, and for the cumulative impacts of multiple intakes

  3. Radiation emergency preparedness in nuclear power plants

    International Nuclear Information System (INIS)

    The purpose of planning for radiation emergency response is to ensure adequate preparedness for protection of the plant personnel and members of the public from significant radiation exposures in the unlikely event of an accident. With a number of safety features in the reactor design and sound operating procedures, the probability of a major accident resulting in the releases of large quantities of radioactivity is extremely small. However, as an abundant cautious approach a comprehensive radiation emergency response preparedness is in place in all the nuclear power plants (NPPs). Radiation Emergency in NPPs is broadly categorized into three types; plant emergency, site emergency and off-site emergency. During off site emergency conditions, based on levels of radiation in the environment, Civil Authorities may impose several counter measures such as sheltering, administering prophylaxis (stable iodine for thyroid blocking) and evacuation of people from the affected area. Environmental Survey Laboratory (ESL) carries out environmental survey extensively in the affected sector identified by the meteorological survey laboratory. To handle emergency situations, Emergency Control Centre with all communication facility and Emergency Equipment Centre having radiation measuring instruments and protective equipment are functional at all NPPs. AERB stipulates certain periodicity for conducting the exercises on plant, site and off site emergency. These exercises are conducted and deficiencies corrected for strengthening the emergency preparedness system. In the case of off site emergency exercise, observers are invited from AERB and Crisis Management Group of Department of Atomic Energy (DAE). The emergency exercises conducted by Nuclear Power Plant Sites have been very satisfactory. (author)

  4. Design of nuclear power plants

    International Nuclear Information System (INIS)

    The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.)

  5. Nuclear power plant simulator software

    International Nuclear Information System (INIS)

    The development is described of software for the simulator of technological equipment of a WWER-440 nuclear power plant unit, using an SM 4-20 computer operating under DOS RV V2 and using a FORTRAN translator. An asynchronous interrupt system is used for kayboard control. All utilities for I/0 operations are written in the macroassembler. The basic concept of the software is shown schematically as are the relations between the program modules and the instructor and student environment. (J.B.). 1 fig

  6. Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I

    International Nuclear Information System (INIS)

    The reactor code PUMA, developed in CNEA, simulates nuclear reactors discretizing space in finite difference elements. Core representation is performed by means a cylindrical mesh, but the reactor channels are arranged in an hexagonal lattice. That is why a mapping using volume intersections must be used. This spatial treatment is the reason of an overestimation of the control rod reactivity values, which must be adjusted modifying the incremental cross sections. Also, a not very good treatment of the continuity conditions between core and reflector leads to an overestimation of channel power of the peripherical fuel elements between 5 to 8 per cent. Another code, DELFIN, developed also in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and current among elements and a more realistic representation of the hexagonal lattice of the reactor. A comparison between results obtained using both methods in done in this paper. (author). 4 refs., 3 figs

  7. Modelling of nuclear power plant decommissioning financing

    International Nuclear Information System (INIS)

    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. (authors)

  8. Atomic power engineering under falsified safety standards

    International Nuclear Information System (INIS)

    In July 1970 the United States Department of Justice accused the American Society of Mechanical Engineers (ASME) of violating the Sherman Antitrust Act and of acting in restraint of trade by restricting the ASME Certificate of Authorization and the use of the Code Symbol Stamps to boilers and pressure vessels manufactured in the United States and Canada. During the succeeding two years attorneys for the parties in the case formulated a Consent Decree without a public confrontation in the Court. Furthermore, the membership of ASME was kept uninformed until October of 1972, after the Consent and Final Judgment had become effective and new procedures had been developed for allowing foreign manufacturers to apply the ASME Code Symbol Stamps to their products. As a consequence, a breakdown in engineered safety standards has been sanctioned and this is undermining the engineering profession's overriding reponsibility to protect the public health and safety. This breakdown of professional responsibility is especially serious in the new technology of atomic power. American insurance companies, which have traditionally written 100% insurance coverage for property damage and third party liability against explosions of high pressure steam boilers bearing the ASME Code Stamp, have refused to write such insurance coverage on nuclear reactors. In the author's opinion there is evidence that the Consent was formulated under collusive proceedings and he calls on the members and the Council of ASME to appeal for dismissal of the Consent Decree. 24 refs

  9. The atlas of large photovoltaic power plants

    International Nuclear Information System (INIS)

    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.)

  10. Geochemical and petromineralogical aspects of the foundation pits of Tarapur atomic power plant reactor buildings 3 and 4, Tarapur, Thane District, Maharashtra

    International Nuclear Information System (INIS)

    Geotechnical investigations that include geochemical and petromineralogical studies are the primary pre-requisite to construct any major civil structures. Two additional nuclear reactors TAPP 3 and 4 are proposed adjoining to already existing TAPP 1 and 2 at Tarapur, Maharashtra to meet the ever growing power demand in the region. Two pits have been excavated for housing the reactor buildings that exposed the CT-3 basalt flow units of Jawahar Formation intruded by dolerite dykes and dykelets. Hydrothermal alterations and fracturing is observed in and around the excavated pits. Systematic mapping followed by collection of samples from the pits and the surrounding area have been studied for detailed petromineralogy and geochemistry. Basalts and dolerites comprise of pyroxene and plagioclase feldspar with rare olivine phenocrysts as major mineral phases with ophitic texture, whereas the fracture filled material is very fine grained with highly altered chloritic mass. Geochemical analysis of the samples indicated that basalts and dolerites have lower WIP (60-65), CIA (30-45) and CIW (35-48) indices. However, the fracture filled material shows bimodal distribution with high weathering indices (30-144) indicating their high degree of alteration. Basalts and dolerites with least altered features from the fracture zone form a good base for hosting reactor building. Based on weathering indices, remedial measures such as scooping of altered material, grouting and cementing the micro fractures are suggested for foundation and construction of TAPP 3 and 4 reactor buildings. (author)

  11. Revised FINAL–REPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004) 2018-SR-02-1

    Energy Technology Data Exchange (ETDEWEB)

    Erika Bailey

    2011-10-27

    The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963. The reactor was tested at low power during the first couple years of operation. Power ascension testing above 1 MW commenced in December 1965 immediately following the receipt of a high-power operating license. In October 1966 during power ascension, zirconium plates at the bottom of the reactor vessel became loose and blocked sodium coolant flow to some fuel subassemblies. Two subassemblies started to melt and the reactor was manually shut down. No abnormal releases to the environment occurred. Forty-two months later after the cause had been determined, cleanup completed, and the fuel replaced, Fermi 1 was restarted. However, in November 1972, PRDC made the decision to decommission Fermi 1 as the core was approaching its burn-up limit. The fuel and blanket subassemblies were shipped off-site in 1973. Following that, the secondary sodium system was drained and sent off-site. The radioactive primary sodium was stored on-site in storage tanks and 55 gallon (gal) drums until it was shipped off-site in 1984. The initial decommissioning of Fermi 1 was completed in 1975. Effective January 23, 1976, DPR-9 was transferred to the Detroit Edison Company (DTE) as a 'possession only' license (DTE 2010a). This report details the confirmatory activities performed during the second Oak Ridge Institute for Science and Education

  12. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

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

  13. Profitability of small-scale power plants

    International Nuclear Information System (INIS)

    Several small-scale power plants have been constructed in Finland during the last few years. Fuel oil and natural gas has been used as a fuel in diesel plants, natural gas in gas-turbine plants, and peat and industrial waste wood in solid fuel fired plants. Larger towns have already acquired combined power and heat generation either in their own power plants or in cooperation with industry. A usual mean of cooperation has been buying of district heat from industrial back-pressure power plants. Numerous small district heat loads still rely on separate heat production. The cheap price of electric power, caused by the good water and nuclear power conditions and long-term delivery contracts, has rendered the construction of small-scale power plants. The fuel prices have been stable for the last few years. The most significant changes have been caused by changing of exchange rate of the Finnish mark and the fuel taxation. Two power plant are reviewed in detail: 6/17 MW peat fired steam power plant and 6/6 MW oil fueled diesel power plant. The electricity prices of these two have been compared with coal condensing power and the electricity tariffs. The price comparisons have been made using the present price level. Energia-Ekono has compiled a new simulation program ELMO, operating in PC-WINDOWS environment, for simulation of cogeneration

  14. Nuclear Power Plant Control and Instrumentation in Pakistan

    International Nuclear Information System (INIS)

    Nuclear reactors generate 15% of the world's supply electric power. The substantial growth in world energy demand is inevitably continuing throughout the next century. Nuclear power which has already paid more than enough for itself and its development, will provide increasing share of electricity production both in the developed and developing countries. For Pakistan with limited natural resources such as oil, gas, and fully tapped hydel power, nuclear power is the only viable option. However, things are not simple for developing countries which embark on nuclear power program. A technical infrastructure should be established as it has been shown by the experience of Control and Instrumentation of the Karachi Nuclear Power Plant. The national report describes the program of Pakistan Atomic Energy Commission in (NPP) Computers, Control and Instrumentation for design, construction, operation, and maintenance of nuclear power plants. (author)

  15. steam power plants re powering with gas turbine review

    International Nuclear Information System (INIS)

    Re powering faith gas turbine means integration of new gas turbine in existing power plant. Such integration yield higher efficiencies lower operating and maintenance costs and reduction in pollution emission. This paper summarizes the results of a feasibility study that inquired the possibilities of such integration in Israel Electric Corporation - IEC's existing steam power plants (oil fired)

  16. Nuclear power plants and the environment

    International Nuclear Information System (INIS)

    The environmental impacts are compared of conventional coal-fired and oil-fired power plants and of nuclear power plants. The values are compared of SO2, NO2, ash and soot emmisions with 133Xe and 85Kr 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.)

  17. 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

  18. Electric power generation in large-scale power plants

    International Nuclear Information System (INIS)

    Future electric power consumption will be depending on the economic development of the Federal Republic of Germany. Thermal power plants are fueled with non-renewable energy sources, i.e. coal, petroleum, natural gas or nuclear power. It is therefore important to assess the global coverage of these energy sources and to take stock of the reserves of the Federal Republic of Germany. If the waste heat left from electric power generation was made use of in dual-purpose power plants total energy consumption could be considerably reduced. Large-scale power plants do have to face and cope with the lack of distribution networks to supply the consumer. (DG)

  19. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    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

  20. Education and training requirements of nuclear power plant personnel

    International Nuclear Information System (INIS)

    This bibliography was compiled by the Scientific Library staff to help in the intensified training program being undertaken by the Philippine Atomic Energy Commission (PAEC) for the nuclear power plant personnel of the Philippines' first nuclear power reactor. This bibliography covers the period 1955 - 1976 of the Nuclear Science Abstracts and is composed of 281 entries. Arrangement of these entries is by broad subject category

  1. Nuclear power plant control system

    International Nuclear Information System (INIS)

    Purpose: To effectively transfer the operation of a nuclear power plant including a bwr type reactor to single load operation in the station with no increase in the neutron flux and water level in the reactor by the combined use of recycle pump trip and feedwater pump trip. Method: Upon rapid load decrease in a turbine generator, at least one of usually operated feedwater pumps and a recycle pump are tripped and the starting for a stand-by feedwater pump is inhibited. This rapidly decreases the recycling flow rate to thereby lower the neutron flux before generation of pressure increase and also decreases the feedwater flow rate to thereby suppress the increase in the water level due to increase in voids, whereby the operation is smoothly transferred to the single load operation in the station. (Horiuchi, T.)

  2. A landscape simulation system for power plants

    International Nuclear Information System (INIS)

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

  3. Financing of nuclear power plant using resources of power generation

    International Nuclear Information System (INIS)

    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

  4. Thoughts on Documentation of Atomic Power Technology

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jeong Hoon; Lee, Hee Won; Song, Ki Chan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Korean Atomic Energy Research Institute (KAERI) has accumulated a number of technology development and research outcomes, including its representative achievements such as atomic energy technology independence and the first export of atomic energy system, since it was established in 1959. With its long history of over 50 years, KAERI has produced a large amount of information and explicit knowledge such as experiment data, database, design data, report, instructions, and operation data at each stage of its research and development process as it has performed various researches since its establishment. Also, a lot of tacit knowledge has been produced both knowingly and not unknowingly based on the experience of researchers who have participated in many projects. However, in the research environment in Korea where they focus overly on the output, tacit knowledge has not been managed properly compared to explicit knowledge. This tacit knowledge is as an important asset as explicit knowledge for an effective research and development. Moreover, as the first generation of atomic energy independence and research manpower retire, their accumulated experience and knowledge are in danger of disappearing. Therefore, in this study, we sought how to take a whole view and to document atomic energy technology researched and developed by KAERI, from the background to achievement of each field of the technology. Comprehensive and systematic documentation of atomic energy technology will establish a comprehensive management system of national atomic energy technology record to make a foundation of technical advancement and development of atomic energy technology. Also, it is expected to be used as an important knowledge and information resource of atomic energy knowledge management system

  5. Simulators predict power plant operation

    Energy Technology Data Exchange (ETDEWEB)

    Peltier, R.

    2002-07-01

    Mix the complexity of a new construction or major retrofit project with today's 'do more with less', a pinch of 'personnel inexperience,' and a dash of 'unintended consequences', and you have got a recipe for insomnia. Advanced simulation tools, however, can help you wring out your design train your operators before the first wire is terminated and just may be get a good night's rest. The article describes several examples of uses of simulation tools. Esscor recently completed a simulation project for a major US utility exploring the potential for furnace/duct implosion that could result from adding higher volumetric flow induced-draft fans and selective catalytic reduction to a 650-MW coal-fired plant. CAF Electronics Inc. provided a full-scope simulator for Alstom's KA24-1 combined-cycle power plant in Paris, France. Computational fluid dynamics (CFD) tools are being used by the Gas Technology Institute to simulate the performance of the next generation of pulverized coal combustors. 5 figs.

  6. 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

  7. Managing Siting Activities for Nuclear Power Plants

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to ''seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world''. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The introduction of nuclear power brings new challenges to States - one of them being the selection of appropriates sites. It is a project that needs to begin early, be well managed, and deploy good communications with all stakeholders; including regulators. This is important, not just for those States introducing nuclear power for the first time, but for any State looking to build a new nuclear power plant. The purpose of the siting activities goes beyond choosing a suitable site and acquiring a licence. A large part of the project is about producing and maintaining a validated

  8. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

  9. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

    International Nuclear Information System (INIS)

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

  10. Dynamic Frequency Response of Wind Power Plants

    DEFF Research Database (Denmark)

    Altin, Müfit

    method has less impact of the power system frequency compared to existing control concepts. Another advantage of the proposed inertial response control has the tuning methodology which can be utilized as a generic approach for any power system with high wind power penetration levels. Additionally, an...... 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...... 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...

  11. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    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)

  12. Fusion power plant availability study

    International Nuclear Information System (INIS)

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

  13. Applications of power from Temelin nuclear power plant

    International Nuclear Information System (INIS)

    The proceedings contain 10 papers of which 9 fall under the INIS scope. They all concern the intentions and possibilities of using heat from nuclear power plants, especially from the Temelin power plant. Waste heat will be used for district heating of adjacent conurbations and for agricultural purposes. Various projects are presented using heat from nuclear power plants, such as greenhouse heating, soil heating, cultivation of algae and fish in warmed-up water. The existing experience is described with the use of heat from the Bohunice nuclear power plant. (M.D.). 15 figs., 6 tabs., 17 refs

  14. World power plant industry in recession

    International Nuclear Information System (INIS)

    Two scenarios of power plant ordering required to meet demand in 2000, based on reasonable assumptions of demand growth, plant lifetimes, and construction lead times, are presented. They result in a high and low of 191 and 75GWe per annum respectively. The scenarios are broken down into regions; Europe, North America, Japan, and less developed countries. It is thought that nuclear power is unlikely to gain a substantial share of the total power plant market. (U.K.)

  15. Completion of a delayed nuclear power plant

    International Nuclear Information System (INIS)

    The Bushehr Nuclear Power Plant was designed and constructed up to nearly 80% by KWU in mid 1970s. The initial design was according to latest safety standards available at that time. In 1979, the German contractor, KWU, stopped the work on BNPP. In January 1994 the Contract for completion of Bushehr Nuclear Power Plant Unit-1 was signed by the AEOI and the Russian firm 'ZAES', an affiliated company of the Russian Ministry of Atomic Energy later on renamed to ASE (Atomstroyexport). In January 1996, based on this new Contract of reconstruction and completion BNPP-1 project was resumed. With Addendum No.1 to the Contract almost all responsibilities with respect to design, construction, erection, procurement, commissioning, and training of the Iranian personnel for operation of the BNPP-1 were given to the Russian firm ASE. The AEOI personnel were assigned the roles and responsibilities for review and approval of the overall completion project. The plant has undergone more than 20 years of suspension. Harsh climatic condition of Bushehr and especially high level of humidity has been a major threat to the maintenance of quality of stored and installed equipment. Due to lack of sufficient funds during 8-year Iran-Iraq war, the preservation of the plant required extensive management efforts. The plant was attacked by Iraq and some damage was made to concrete and steel containment and polar crane of BNPP-1. In order to continue the projects talking into account the current safety standards, the Iranian Nuclear Regulatory Authority (INRA), in co-operation with the IAEA and GAN, has developed the necessary safety documents. A program for integration of existing KWU equipment, buildings and structures is started. The cumulative progress of the completion has reached 62% ny September 2003. It includes: design and engineering progress - 85%, including licenses; Repair works of buildings and structures are completed and required certificates are issued and as-built design

  16. Implementation of condition-based maintenance at the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Condition-Based Maintenance (CBM) techniques have been successfully used in on a variety of equipments in US nuclear power plants for the past twenty years. These techniques have had the benefit of improving overall plant reliability and availability while at the same time reducing maintenance costs by as much as fifty percent. The typical pay-back period for the implementation of CBM is less than one year. Emergency diesel engines are one specific piece of equipment for which CBM has been particularly successful in US nuclear power plants. The Japan Atomic Power Company (JAPC) began to implement CBM for rotating components three years ago and, also has recently begun to apply DG diagnostic techniques at three nuclear power plants with the technical support by MPR associates, Inc. The application of CBM to Japanese nuclear power plants is similar to US nuclear power plants but differences in the regulatory structure and current maintenance practices in Japan results in some unique challenges. This paper provides a description of the CBM methods used for diesel engines in nuclear standby service, a summary of the experience with these methods at US nuclear power plants, and experience with the application of these methods to JAPC nuclear power plants. (author)

  17. Investigation toward laser driven IFE power plant

    International Nuclear Information System (INIS)

    Inertial fusion energy (IFE) is becoming feasible due to the increasing understanding of implosion physics. Reactor technology issues have begun to be developed. Based on the conceptual design of Laser Driven IFE Power Plant, the technical and physical issues have been examined. R and D on key issues that affect the feasibility of power plant have been proceeded taking into account the collaboration in the field of laser driver, fuel pellet, reaction chamber and system design. It is concluded that the technical feasibility of IFE power plant seems to be reasonably high. Coordination and collaboration scheme of reactor technology experts in Japan on Laser Driven IFE Power Plant is being proceeded. (author)

  18. Methodology for Scaling Fusion Power Plant Availability

    Energy Technology Data Exchange (ETDEWEB)

    Lester M. Waganer

    2011-01-04

    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.

  19. Methodology for Scaling Fusion Power Plant Availability

    International Nuclear Information System (INIS)

    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.

  20. Power source facility inside of nuclear power plant

    International Nuclear Information System (INIS)

    The present invention simplifies power source facilities inside of a nuclear power plant and enables to provide countermeasures for troubles and inspection of one main transformer during plant operation. Namely, power in the plant is supplied to bus in ordinary use from a main power generator by way of a directly-coupled transformer in the plant during plant operation. Simultaneously, the power inside of the plant is supplied to a bus in non-ordinary use by way of a first communication bus. In this case, an onload tap changer of the direct transformer in the plant controls the voltage on the secondary side of the directly-coupled transformer to a lower level. On the other hand, when a load switcher of the power generator is opened under a predetermined condition, and the main power generator is disconnected from the main transformer and the directly-coupled transformer in the plant, power inside of the plant is supplied to the bus in ordinary use from the secondary side of the main transformer. In this case, the onload tap changer of the main transformer controls the voltage of the secondary side of the main transformer to a higher level. (I.S.)

  1. Control of power plants and power systems. Proceedings

    International Nuclear Information System (INIS)

    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)

  2. 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 ...

  3. Future requirements for fossil power plants

    Directory of Open Access Journals (Sweden)

    Spliethoff H.

    2013-06-01

    Full Text Available The fast increasing installation of technologies to convert renewable energy into power influences the operation of conventional power plants. New requirements on the technology, on the operation and on the economic have to be considered for already running and future power plants. Currently, first experiences with such a production and market situation are available. Technologies are discussed to store power and to reduce CO2 emissions. New compensation models are necessary to enable economic operation of fossil power plants in base load. This article gives a short review about available technologies and future challenges.

  4. Economy of small-scale power plants

    International Nuclear Information System (INIS)

    The basic requirement for profitable generation of power and heat is sufficient and even heat load. The investment required by a plant based on cogeneration is always higher than that of a plant producing only heat, and hence the full time operation of the plant should be ensured since the beginning of the plant operational age. The second requirement for profitable operation of a small-scale power plant is the homogenous heat and power consumption profiles. Because the plants always cause remarkable capital costs and other fixed costs it is important to make an economic survey of the costs before the decision making in the preliminary planning phase. The presentation gives a review of the factors effecting on the economy of small-scale power plant, the distribution of the costs, and the methods used for investigation of the economy are reviewed

  5. Fukushima nuclear power plant accident was preventable

    Science.gov (United States)

    Kanoglu, Utku; Synolakis, Costas

    2015-04-01

    On 11 March 2011, the fourth largest earthquake in recorded history triggered a large tsunami, which will probably be remembered from the dramatic live pictures in a country, which is possibly the most tsunami-prepared in the world. The earthquake and tsunami caused a major nuclear power plant (NPP) accident at the Fukushima Dai-ichi, owned by Tokyo Electric Power Company (TEPCO). The accident was likely more severe than the 1979 Three Mile Island and less severe than the Chernobyl 1986 accidents. Yet, after the 26 December 2004 Indian Ocean tsunami had hit the Madras Atomic Power Station there had been renewed interest in the resilience of NPPs to tsunamis. The 11 March 2011 tsunami hit the Onagawa, Fukushima Dai-ichi, Fukushima Dai-ni, and Tokai Dai-ni NPPs, all located approximately in a 230km stretch along the east coast of Honshu. The Onagawa NPP was the closest to the source and was hit by an approximately height of 13m tsunami, of the same height as the one that hit the Fukushima Dai-ichi. Even though the Onagawa site also subsided by 1m, the tsunami did not reach to the main critical facilities. As the International Atomic Energy Agency put it, the Onagawa NPP survived the event "remarkably undamaged." At Fukushima Dai-ichi, the three reactors in operation were shut down due to strong ground shaking. The earthquake damaged all offsite electric transmission facilities. Emergency diesel generators (EDGs) provided back up power and started cooling down the reactors. However, the tsunami flooded the facilities damaging 12 of its 13 EDGs and caused a blackout. Among the consequences were hydrogen explosions that released radioactive material in the environment. It is unfortunately clear that TEPCO and Japan's principal regulator Nuclear and Industrial Safety Agency (NISA) had failed in providing a professional hazard analysis for the plant, even though their last assessment had taken place only months before the accident. The main reasons are the following. One

  6. Siting studies for new nuclear power plants in Argentina

    International Nuclear Information System (INIS)

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

  7. Nuclear power plant functions: overview, maintenance, design practices, training

    International Nuclear Information System (INIS)

    The author gives a history of the nuclear industry in the US beginning with the Atoms for Peace Proposal in 1954 and summarizes the nuclear industry's importance in the realm of electric power production today. The primary problems facing the domestic nuclear industry are identified as the lengthening schedules for plant licensing and construction, and the associated uncertainty in plant costs and difficulty in financing, and the erosion of public confidence. Views on technological approaches to the future of nuclear power and the role regulation will play in the future as a fundamental force are discusses in the paper. Also discussed are the importance of standardization of advanced reactor designs and quality assurance

  8. CANDU 9 nuclear power plant design description

    International Nuclear Information System (INIS)

    Atomic Energy of Canada limited (AECL) has make significant design improvements in the latest CANDU nuclear power plant (NPP)-the CANDU 9. The CANDU 9 operates with the energy efficient heavy water moderated reactor and natural uranium fuel and utilizes proven technology. The CANDU 9 NPP design is similar to the world leading CANDU 6 but is based upon the single unit adaptation of the 900 MWe class reactors currently operating in Canada (as multiunit configurations). The CANDU 9 NPP was developed as part of the comprehensive AECL product development program which addresses all aspects of CANDU technology including such disciplines as safety, reactor systems and components, constructability, instrumentation and control, health and environment, fuel and fuel cycles and heavy water systems. This paper will provide an overview for some of the key features of the CANDU 9 NPP such as plant layout, safety enhancements and operability improvements implemented in this design as well as outlining some of the advantages that can be expected by the operating utility

  9. 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.

  10. New nuclear power plants for Ontario

    International Nuclear Information System (INIS)

    Towards the end of this year the Ontario government will select the technology for its future nuclear power plants. To clarify the differences between the contending reactors I have put together the following quick overview. Ontario's requirement is for a stand-alone two-unit nuclear power plant to provide around 2,000 to 3,500 MWe of baseload generating capacity at a site to he specified with an option for one or two additional units. It is likely that the first units will be located at either the Darlington site near Bowmanville or the Bruce site near Kincardine. However the output from the Bruce site is presently transmission constrained. All nuclear-electric generation in Ontario comes from Atomic Energy of Canada Limited's (AECL) CANDU reactors at Pickering, Darlington and Bruce. The contenders are, AECL's 1085 MWe (net) ACR-1000 (Advanced CANDU Reactor), Westinghouse Electric Company's 1117 MWe (net) AP1000 (Advanced Passive), AREVA NP's 1600 MWe (net) U.S. EPR (United States Evolutionary Pressurized Reactor) and the 1550 MWe (net) GE Hitachi Nuclear Energy's ESBWR (Economic and Simplified Boiling Water Reactor). Westinghouse has Toshiba as a majority shareholder, AREVA has the government of France as a majority shareholder and GE-Hitachi has GE as the major shareholder. AECL is a federal crown corporation and is part of Team CANDU consisting of Babcock and Wilcox Canada, GE-Hitachi Nuclear Energy Canada Inc., Hitachi Canada Limited and SNC-Lavalin Nuclear Inc. Generally the engineering split in Team CANDU would be, AECL, Mississauga, Ontario, responsible for the design of the nuclear steam plant including reactor and safety systems; Babcock and Wilcox Canada, Cambridge, Ontario, responsible for supply of the steam generators and other pressure retaining components; GE-Hitachi Nuclear Energy Canada Inc., Peterborough, Ontario for the fuel handling equipment; Hitachi Canada Limited, Mississauga, for the balance of plant steam to electricity conversion

  11. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    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.)

  12. Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.

    Science.gov (United States)

    Whitelaw, Robert L.

    The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…

  13. Maintenance of nuclear power plant

    International Nuclear Information System (INIS)

    Maintenance action of nuclear power plant (NPP) was described. Maintenance of NPP aimed at assurance of required function of NPP's equipment so as to prevent release of radioactive materials into the environment as well as attainment of stable operation of NPP. Philosophy of NPP safety was based on defense-in-depth or multiple barriers requiring specified function for the equipment. Preventive maintenance was essential to NPP's equipment and the scope of maintenance was decided on priority with adequate method and frequency of inspection. Most inspection was conducted during periodic inspection at outage. Repair or improvement works were performed if needed. Periodic inspection period was very long and then capacity factor of NPP was low in Japan compared with foreign data although frequency of unscheduled shutdown was very low. Introduction of reability- centered maintenance was requested based on past experiences of overhaul inspection. Technical evaluation of aged NPP had been conducted on aging phenomena and promotion of advanced maintenance was more needed. (T. Tanaka)

  14. Thermal power plant simulation and control

    CERN Document Server

    Flynn, Damian

    2013-01-01

    Contributors of world-class excellence are brought together in Thermal Power Plant Simulation and Control to illustrate how current areas of research can be applied to power plant operation, leading to enhanced unit performance, asset management andplant competitiveness through intelligent monitoring and control strategies.

  15. Quality assurance in nuclear power plant

    International Nuclear Information System (INIS)

    The factors related to the licensing procedures of a nuclear power plant (quality assurance and safety analysis) are presented and discussed. The consequences of inadequate attitudes towards these factors are shown and suggestions to assure the safety of nuclear power plants in Brazil are presented. (E.G.)

  16. Lessons learned from existing biomass power plants

    Energy Technology Data Exchange (ETDEWEB)

    Wiltsee, G.

    2000-02-24

    This report includes summary information on 20 biomass power plants, which represent some of the leaders in the industry. In each category an effort is made to identify plants that illustrate particular points. The project experiences described capture some important lessons learned that lead in the direction of an improved biomass power industry.

  17. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

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

  18. Working in a virtual power plant

    International Nuclear Information System (INIS)

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

  19. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    In the third quarter of 1993, all of Finland's four nuclear power plant units were in power operation, with the exception of the annual maintenance outages of the Loviisa units. The load factor average of the plant units was 83.6 %. None of the events which occurred during this annual quarter had any bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

  20. Nuclear power plants for protecting the atmosphere

    International Nuclear Information System (INIS)

    Some figures are presented comparing date on the CO2 emission and oxygen consumption of nuclear, natural gas fired, advanced coal fired and oil fired power plants, for the same amounts of electricity generated. The data were deduced from the Paks Nuclear Power Plant, Hungary. (R.P.)

  1. Nuclear power plant risk management

    International Nuclear Information System (INIS)

    This book collects papers on nuclear plant risk management. Topics include: basic concepts in risk analysis and decision theory; establishing integrated plant models; core and containment response; and site modeling and consequences

  2. The operating staff of nuclear power plants

    International Nuclear Information System (INIS)

    The training of its staff is one of the pillars of the safe and economical operation of a power plant. This is why power plant owners began to systematically train their staff already in the 50s, and why they created central training facilities. Staff members who have undergone this training make an indispensable contribution to the acceptedly high safety and availability of German power plants. The substantial cost of creating training facilities and of schooling plant staff is considered to be an investment for the future. Low labour turnover permits careful observation and development of staff and leads to a high standard of knowledge and experience. (orig./HSCH)

  3. Super-simulator for nuclear power plant

    International Nuclear Information System (INIS)

    The super-simulator is a conceptual name for future innovative simulators of nuclear power plants which surpass, to a large extent, the capabilities and performances of existing nuclear power plant simulators for operator training, plant analyzers for engineering studies or computer codes for dynamics analysis. Such super-simulators will be realized by employing highly advanced methods of mathematical modeling of the physical chemical and other related processes in the nuclear power plants and innovative methods of numerical computation using rapidly evolving high performance computing systems. (author)

  4. Harmonics in a Wind Power Plant: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Preciado, V.; Madrigal, M.; Muljadi, E.; Gevorgian, V.

    2015-04-02

    Wind power generation has been growing at a very fast pace for the past decade, and its influence and impact on the electric power grid is significant. As in a conventional power plant, a wind power plant (WPP) must ensure that the quality of the power being delivered to the grid is excellent. At the same time, the wind turbine should be able to operate immune to small disturbances coming from the grid. Harmonics are one of the more common power quality issues presented by large WPPs because of the high switching frequency of the power converters and the possible nonlinear behavior from electric machines (generator, transformer, reactors) within a power plant. This paper presents a summary of the most important issues related to harmonics in WPPs and discusses practical experiences with actual Type 1 and Type 3 wind turbines in two WPPs.

  5. 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.

  6. Human factors in nuclear power plant operations

    International Nuclear Information System (INIS)

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants

  7. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants. (orig.)

  8. Safety culture in nuclear power plants

    International Nuclear Information System (INIS)

    Experience shows that German nuclear power plants have always been operated reliably and safely. Over the years, the safety level in these plants has been raised considerably so that they can stand any comparison with other countries. This is confirmed by the two reports published by the Federal Ministry for the Environment on the nuclear safety convention. Behind this, there must obviously stand countless appropriate 'good practices' and a safety management system in nuclear power plants. (orig.)

  9. Linguistic control of a nuclear power plant

    International Nuclear Information System (INIS)

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

  10. Program increasing of nuclear power plant safeness

    International Nuclear Information System (INIS)

    The results achieved within the project of national task 'Program increasing of nuclear power plant safeness' are presented in the document. The project was aimed to extend and deepen activities relating to safety increase of nuclear power units WWER-440 which play significant part in electricity production in the Slovak Republic. The application of advanced foreign calculating programs and calculation of radionuclide spreading in environment and techniques will influence the increase of extent, quality and international acceptance of safety analysis of nuclear power plant blocks WWER-440 and the risk valuation from operating nuclear power plants. Methodic resources for coping in emergency situation in nuclear energetics will be used for support in decision making in real time during radiation emergency on nuclear plant, region and state level. A long-term strategy in dealing with burnt fuel and radioactive substance formatting during nuclear power plant liquidation particularly with waste which is un acceptable in regional dump, has developed into a theoretical and practical preparation of solvable group for operating the converting centre Bohunice and in inactivating the nuclear power plant A-1. The diagnostic activities in nuclear power plants in the Slovak Republic have been elaborated into a project of norm documents in accordance with international norms for diagnostic systems. Presentation of new technologies and materials for repairs and reconstructions of components and nuclear power plant knots qualify increase in their reliability, safety and life. New objective methods and criterions for valuation and monitoring of the residual life and safety of fixed nuclear power plants. Results of problem solving linked with connecting the blocks of nuclear power plants to frequency regulation in electric network in the Slovak Republic are also presented in the document

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

    International Nuclear Information System (INIS)

    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.)

  12. The World Power Conference and atomic energy

    International Nuclear Information System (INIS)

    The possibility that emerged after the last World War that useful power could be produced from nuclear fission led to optimistic estimates that nuclear power would prove to be the solution to the world's energy problems. The possible advantages of nuclear methods of power production compared with conventional means are discussed at the World Power Conference. The 1962 Conference with its theme 'The Changing Pattern of Power' will undoubtedly attract great interest in a world where the change-over from conventional to nuclear fuels for power production has started in some countries and is being actively examined in others. It is generally being realized that even though a country may possess indigenous supplies of uranium or thorium minerals, the building up of a nuclear industry i s a long and expensive process and the alternative of depending on countries more advanced in nuclear technology for the supply of materials, skill and know-how is costly in foreign exchange and international prestige. Many of the industrialized countries, still possessing supplies of conventional fuels, are preparing for the day when their reserves will become depleted and are embarking on training schemes to ensure a continuing supply of engineers and scientists skilled in nuclear arts

  13. Nuclear power plant after Fukushima incident: Lessons from Japan to Thailand for choosing power plant options

    OpenAIRE

    Tatcha Sudtasan; Komsan Suriya

    2012-01-01

    This study evaluates four power plant options in Thailand to suggest whether the country should adopt nuclear power plants. It includes a scenario that nuclear power plants are forced to be shut because of natural disaster like what happened at Fukushima Daiishi nuclear power plant in Japan. The results found that, in terms of net present value both in duration of 30 and 50 years, nuclear power plants is the best choice under certainty of no severe natural disaster that would interrupt the op...

  14. Bid Preparation and Evaluation for Nuclear Power Plant Project Management

    International Nuclear Information System (INIS)

    Bid preparation and evaluation is one of the main activities in Nuclear Power Plant Project management. International Atomic Energy Agency guide and Korean experience was studied for Malaysian requirement in realization of first Nuclear Power Plant. Several aspects shall be taken into consideration such as political scenario, financial capabilities, sitting, human resource, technologies, fuel supplies and decommissioning for long term exceeded hundred years. Bidding process and activities is proposed for our country requirement. The main activities included but unlimited to Bid Invitation Specification, Bid Evaluation Process, Technical Evaluation, Economic Bid Evaluation and Contracting. On the end of day, Malaysia need safe and reliable Nuclear Power Plant. Malaysian Economic Transformation Programme also get benefit from spin-off localization products and services as well as Technology Transfer Programme. (author)

  15. Laser technologies for the nuclear power plant maintenance

    International Nuclear Information System (INIS)

    The recent improvement of laser technologies will contribute to the maintenance of nuclear power plants. The Japan Atomic Energy Agency developed a specially designed probing system was developed to inspect and repair the cracks of the welded beads of the heat exchanger tubes of nuclear power plants. Eddy current testing detected inner wall cracks in heat exchanger tubes. The tubes thickness was 4.5 mm and the inner diameter was 23 mm. The minimum detectable depth of the cracks was 10% of the tube thickness. Endoscope observation confirmed the cracks along the welded beads. Laser welding by a 300 W compact fiber laser successfully repaired them. The probing system will operate in new nuclear power plants with various laser monitoring technologies for coolant pipes. (author)

  16. Operating experience with nuclear power plants 2013

    International Nuclear Information System (INIS)

    The VGB Technical Committee 'Nuclear Plant Operation' has been exchanging operating experience about nuclear power plants for more than 30 years. Plant operators from several European countries are participating in the exchange. A report is given on the operating results achieved in 2013, events important to plant safety, special and relevant repair, and retrofit measures from Belgium, Germany, Finland, the Netherlands, Switzerland, and Spain. (orig.)

  17. Decontamination and decommissioning of the Shippingport Atomic Power Station - a retrospective

    International Nuclear Information System (INIS)

    The 72 MW Shippingport Atomic Power Station (SAPS) first achieved criticality in December 1957 and was operated thereafter for almost 25 years. During the period October 1984 to December 1989, the U.S. Department of Energy (DOE) carried out the Shippingport Decommissioning Project, marking the world's first commercial sized nuclear power plant decommissioning. The experience gained from this project established the foundation for engineering, planning, and cost estimating for future decommissioning projects

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

    International Nuclear Information System (INIS)

    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

  19. Safety indices (Set of indices used by the State Surveillance over Nuclear Safety, Czechoslovak Atomic Energy Commission, to evaluate the operating safety of nuclear power plants in Czechoslovakia, and results of evaluation for the period of 1991 to June 1992)

    International Nuclear Information System (INIS)

    Fields of operation of nuclear power plants are identified to which the set of safety indices can be applied. The choice was made with regard to the State Surveillance needs and requirements and to the feasibility of obtaining a sufficient volume of objective data. Examined were significant events (unscheduled emergency shutdowns, violation of the safe operation limits and conditions, etc.), function of the safety systems and their operability, hermeticity of barriers, reliability of fuel, radiation protection, and environmental protection (specific activity of radioactive releases). The results obtained serve as a source of information on the trends in the nuclear power plant operation, for the identification of weak spots in the plant operation, for determining the aims of inspection activities and as a document in support of decisions made and requirements imposed. (M.D.). Figs., diagrams

  20. Transient analysis models for nuclear power plants

    International Nuclear Information System (INIS)

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

  1. Economic evaluation of tokamak power plants

    International Nuclear Information System (INIS)

    This study reports the impact of plasma operating characteristics, engineering options, and technology on the capital cost trends of tokamak power plants. Tokamak power systems are compared to other advanced energy systems and found to be economically competitive. A three-phase strategy for demonstrating commercial feasibility of fusion power, based on a common-site multiple-unit concept, is presented

  2. The licensing procedure for construction and operation of nuclear power plants

    International Nuclear Information System (INIS)

    The licensing procedure for the construction and operation of the nuclear power plants in Brazil is analysed, according to the International Atomic Energy Agency orientation. The risks related to the nuclear energy is also emphasized. (A.L.)

  3. 77 FR 65417 - Northern States Power Company (Prairie Island Nuclear Generating Plant Independent Spent Fuel...

    Science.gov (United States)

    2012-10-26

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Northern States Power Company (Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation); Notice of Atomic Safety and Licensing Board Reconstitution Pursuant to 10 CFR...

  4. Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    The paper deals with the legal background, the role of the 'Bund' (Federation) and the 'Laender' (States) in the field of atomic energy and radiation protection law and the licensing procedure for nuclear power plants. (RW)

  5. Training program for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Nuclear power generation in Japan reached 24.7% of its electric power supply with its capacity and time availability factors of 76.2% and 77.1%, respectively (in the calendar year 1986 - as of December 31, 1986). One of the reasons for such high performance is attributable to high quality of operating and maintenance personnel in the nuclear power plants. Ministry of International Trade and Industry of the Japanese Government has an overall responsibility with relation to the safety regulations and supervises all scope of training, while the Thermal and Nuclear Power Engineering Society is authorized to conduct licensing activities to qualify the chief shift supervisor of nuclear power plant operation and individual utility companies are required to train their plant operating and maintenance personnel. General status of training for plant personnel is briefly described in this paper, touching the practical education and training systems of utility companies and operation and maintenance training facilities

  6. Fuel requirements (without reprocessing) for Iran 1, 2, 3 and 4 nuclear power plants

    International Nuclear Information System (INIS)

    By use of a computer program written by the Nuclear Power Plant Management of the Atomic Energy Organization of Iran, the Yellow Cake, natural uranium and separative work unit (SWU) for the first core and ten reloads of the Iran 1, 2, 3 and 4 Nuclear Power Plants have been calculated for different tail assays. (author)

  7. Biomass-fueled power plants in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Raiko, M. [IVO Power Engineering Ltd., Vantaa (Finland); Hulkkonen, S. [Imatran Voima Oy, Vantaa (Finland)

    1997-07-01

    Combined heat and power production (CHP) from biomass is a commercially viable alternative when district heat or process steam is needed in small towns or in a process industry. The high nominal investment cost of a small power plant that uses local biomass fuels is compensated by the revenues from the heat. The price of the district heat or the steam generated in the CHP-plant can be valued at the same price level as the heat from a mere steam boiler. Also, the price of heat produced by a small-generation-capacity plant is local and higher, whereas electricity has a more general market price. A typical small Finnish CHP-plant consists of a bubbling fluidized bed boiler and a simplified steam turbine cycle generating 4 to 10 MW of electricity and 10 to 30 MW of district heat or process steam. There are about 10 power plants of this type in commercial operation in Finland. As a whole, biomass, which is used in more than 200 plants, provides about 20% of the primary energy consumption in Finland. Roughly half of these produce only heat but the rest are combined heat and power plants. The majority of the plants is in pulp and paper industry applications. Imatran Voima Oy (IVO) is the biggest energy producer in Finland. IVO builds, owns and operates several biomass-fired power plants and carries out active R and D work to further develop the biomass-fueled small power plant. This paper discusses the experiences of the biomass-fueled power plants. (author)

  8. Technical services for power plants and energetic objects

    Energy Technology Data Exchange (ETDEWEB)

    Cieplak, J.; Kuszke, H.; Rozewicz, Z.; Suchorab, A.

    1978-01-01

    The paper gives a survey of organization, services, and tasks of ENERGOPOMIAR, a measurement and research institution directly subordinate to the Minister for Energetics and Atomic Energy. The institution has great authority in the field of quality control of machinery and equipment as well as in the field of operating problems and expert opinions. An appendix lists selected domestic and foreign power plants and stations for which ENERGOPOMIAR has carried out the work described in the article.

  9. The spherical tokamak fusion power plant

    International Nuclear Information System (INIS)

    The design of a 1GW(e) steady state fusion power plant, based on the spherical tokamak concept, has been further iterated towards a fully self-consistent solution taking account of plasma physics, engineering and neutronics constraints. In particular a plausible solution to exhaust handling is proposed and the steam cycle refined to further improve efficiency. The physics design takes full account of confinement, MHD stability and steady state current drive. It is proposed that such a design may offer a fusion power plant which is easy to maintain: an attractive feature for the power plants following ITER. (author)

  10. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost all the time in the first quarter of 1992. The load factor average was 99.8%. All events which are classified on the International Nuclear Event Scale were level 0/below scale on the Scale. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure, originating from the nuclear power plants, were detected in samples collected in the vicinity of the nuclear power plants

  11. Advantages of butterfly valves for power plants

    International Nuclear Information System (INIS)

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

  12. Nuclear power plants in Europe 1989

    International Nuclear Information System (INIS)

    The report covers the situation of the nuclear power plant industry in 18 European countries, seven belonging to the COMECON. There are at present 229 nuclear power plant units in operation, producing 168 087 MWe. Sixty-six units are under construction and will add a capacity of 62 355 MWe, and further planned 33 units are designed to supply 32 872 MWe. This results in a total of 328 nuclear power plant units with a capacity of 263 318 MWe. The number of units in operation in West European countries including Yugoslavia was 153 in April 1989, totalling a capacity of 122 809 MWe. (orig./UA)

  13. Conduit Dynamics in Herand Power Plant

    OpenAIRE

    Sletten, Siri Skyberg

    2015-01-01

    The aim of this master thesis was to conduct a stability analysis of Herand power plant. Herand is a hydropower plant under planning by Herand Kraft, and it is planned to have a generator of 27MVA. The size of the power plant puts it under the requirements in Norway stating that all generators above 10MVA must have frequency regulation and be able to operate in an isolated grid. This paper presents a conducted analysis of Herand that examines whether the plant will be able to meet these requi...

  14. Electromagnetic compatibility of nuclear power plants

    International Nuclear Information System (INIS)

    Lately, there has been a mounting concern about the electromagnetic compatibility of nuclear-power-plant systems mainly because of the effects due to the nuclear electromagnetic pulse, and also because of the introduction of more-sophisticated and, therefore, more-susceptible solid-state devices into the plants. Questions have been raised about the adequacy of solid-state-device protection against plant electromagnetic-interference sources and transients due to the nuclear electromagnetic pulse. In this paper, the author briefly reviews the environment, and the coupling, susceptibility, and vulnerability assessment issues of commercial nuclear power plants

  15. Power plant technology 2014. Strategies, systems engineering and operation

    International Nuclear Information System (INIS)

    The book on power plant technology 2014 (strategies, systems engineering and operation) covers the following issues: Climate, politics and economy; wind power; fossil-fuel power plants, flexible power plants - plant operation, flexible power plants- materials, materials for energy technology, fuel feed and incineration, modeling of the water-vapor-circuit, corrosion, deposits and cleaning, vapor turbines, GUD power plants, fluidized bed combustion, energetic biomass use, combined heat and power generation and decentralized units, storage facilities, emissions - mitigation and measuring techniques.

  16. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    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

  17. Development of power generation and nuclear power plant siting

    International Nuclear Information System (INIS)

    An overview is presented of Czechoslovak WWER type nuclear power plants in operation, under construction and planned. Regional geological surveying is being performed for nuclear power plant siting, covering an area of about 100 to 200 km in radius, as well as engineering and geological surveying aimed at obtaining data on the bearing capacity and stability of the area, on the subsidence of foundation soil due to construction, on ground water level, etc. The basic engineering and geological properties of suitable nuclear power plant sites are listed. A description is given of the method of seismic subdivision of the site into micro-areas and of the system of automatic earthquake protection used for securing the seismic safety of the power plants. (E.J.). 3 refs

  18. Optimal control systems in hydro power plants

    International Nuclear Information System (INIS)

    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)

  19. Sustainability in Large Power Plants

    OpenAIRE

    Faria, Roberto Censi; Kniess, Cláudia Terezinha; Maccari, Emerson Antonio

    2012-01-01

    No business activity today can be implemented without take into account the aspects of sustainability. The concept of sustainable development that was born of the years 1970 and 1980 and was enshrined in the concept of the three pillars of John Elkington - economic, social and environmental issues, the "triple bottom line" is a constraint for all types of enterprises, especially for large hydropower plants. Large hydropower plants have been for a while the great enemy of development, because ...

  20. Environmental effects of electric power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ragozin, D.A.

    1989-04-01

    Argues that the increased concern about environmental damage that has appeared since the advent of reconstruction (perestroika) and other political reform in the USSR must not be allowed to stand in the way of economic development. Identifies an ecological extremism that resists development such as construction of power plants and electrification and that will result in a lowering of living standards. Dismisses idea that alternative power sources such as wind power and solar power are feasible on a large scale and claims that large-scale hydroelectric power plants are no more harmful to the environment than small-scale plants. Dismisses as scientifically unfounded the theories of several eminent scientists who have published works and made films on several environmental aspects including energy and environment in Siberia, claiming that they attack hydroelectric power while ignoring the air, water and ground pollution from coal fired plants such as the KATEhK Kansk Achinsk fuel and power complex and underestimating the difficulty in purifying gaseous emissions. Concludes that the primary subject of protection should be man's health and inheritance and the main way of achieving this aim is to intensify the construction of hydroelectric power plants that do not produce harmful emissions, do not affect the global climate, have an inexhaustible energy resource and will help preserve valuable resources such as coal, oil and gas.

  1. Power plant construction. Plan, build, repair

    International Nuclear Information System (INIS)

    Modern thermal power plants can now convert up to 90 % of the energy input into electricity. This increase in efficiency has been made possible through technological progress, but also through improvements in power plant construction. Despite a distinct rise in the proportion of renewable energies in electricity supplies, traditional power stations are still responsible for guaranteeing a large share of our energy supplies. Air pollution control, noise control, protection of natural waters and soils plus careful use of resources are the key themes in the design, construction and maintenance of power plants. Publishing house Ernst and Sohn provides competent, up-to-date information for civil and structural engineers entrusted with such challenging engineering tasks. The special issue ''Power Plant Construction'' brings together the appropriate articles from the journals ''Bautechnik'', ''Stahlbau'', ''Beton- und Stahlbetonbau'' and ''Geomechanics and Tunnelling''. The themes in this compendium cover a wide range of topics, including analysis and design of power plant installations, power station refurbishment and maintenance, special structures such as cooling towers, chimneys and boiler house frames plus the engineering aspects of coal-fired, nuclear and hydroelectric power stations. Reports on current products and projects complement the technical papers. (orig.)

  2. Availability Improvement of German Nuclear Power Plants

    International Nuclear Information System (INIS)

    High availability is important for the safety and economical performance of Nuclear Power Plants (NPP). The strategy for availability improvement in a typical German PWR shall be discussed here. Key parameters for strategy development are plant design, availability of safety systems, component reliability, preventive maintenance and outage organization. Plant design, availability of safety systems and component reliability are to a greater extent given parameters that can hardly be influenced after the construction of the plant. But they set the frame for maintenance and outage organisation which have shown to have a large influence on the availability of the plant. (author)

  3. Fault simulator trainer for nuclear power plants

    International Nuclear Information System (INIS)

    A new nuclear power plant control simulator, developed at Karlsruhe for training operators, is described, based on an office type minicomputer with visual displays representing the various relevant reactor parameters, commands, controls status and safety arrangements. (S.R.)

  4. EPA Facility Registry Service (FRS): Power Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains data on power plants, based on the Energy Information Administration's EIA-860 dataset and supplemented with data from EPA's Facility...

  5. Industrial accidents in nuclear power plants

    International Nuclear Information System (INIS)

    In 12 nuclear power plants in the Federal Republic of Germany with a total of 3678 employees, 25 notifiable company personnel accidents and 46 notifiable outside personnel accidents were reported for an 18-month period. (orig./HP)

  6. Environmental hazards from nuclear power plants

    International Nuclear Information System (INIS)

    The article discusses the radiation exposure due to nuclear power stations in normal operation and after reactor incidents. Also mentioned is the radiation exposure to the emissions from fuel reprocessing plants and radioactive waste facilities. (RW/AK)

  7. Recommended general safety requirements for nuclear power plants

    International Nuclear Information System (INIS)

    This report presents recommendations for a set of general safety requirements that could form the basis for the licensing of nuclear power plants by the Atomic Energy Control Board. In addition to a number of recommended deterministic requirements the report includes criteria for the acceptability of the design of such plants based upon the calculated probability and consequence (in terms of predicted radiation dose to members of the public) of potential fault sequences. The report also contains a historical review of nuclear safety principles and practices in Canada

  8. Training of nuclear power plant operating personnel

    International Nuclear Information System (INIS)

    Proceedings are presented containing 13 papers on the training of nuclear power plant personnel, especially personnel of WWER type plants. The questions are discussed such as care of personnel, the position of operators and maintenance workers, factors affecting their reliable work, the human factor in reliability and safety of big power facilities, the assurance of a standard system of operators' training with associated social and sociological aspects, the development of psychodiagnostic methodologies for testing and selecting workers for individual jobs. (B.S.)

  9. Nuclear power plants in Germany. Performance 2011

    International Nuclear Information System (INIS)

    The report on the performance nuclear power plants in Germany in 2011 includes the operational results, safety analyses, revisions, quality management, environmental management, status of radioactive waste management, and eventual programs (TACIS, WANO) for the nuclear power plants Biblis A, Biblis B, Brokdorf KBR, Brunsbuettel KKB, Emsland KKE, Grafenrheinfeld KKG, Grohnde KWG, Gundremmingen KRB B, Gundremmingen KRB C, Isa KK1, Isar KK2, Kruemmel KKK, Neckarwestheim GKN I, Neckarwestheim GKN II, Philippsburg KKP 1, Philippsburg KKP 2, and Unterweser KKU.

  10. Reducing imbalances with virtual power plant operation

    OpenAIRE

    Zapata Riveros, Juliana; D'HAESELEER, William; Vandewalle, Jeroen

    2013-01-01

    The penetration of a large amount of distributed generation technologies with intermittent output, such as photovoltaic installations and wind turbines, yields an important challenge to the electric grid. This work illustrates the case of a virtual power plant that consists of several Cogeneration devices (CHP) systems and photovoltaic (PV) installations. The virtual power plant (VPP) operator bids electricity to the day-ahead market using the forecast for solar irradiation. In real time,...

  11. Fire protection at nuclear power plants

    International Nuclear Information System (INIS)

    The guide presents specific requirements for the design and implementation of fire protection arrangements at nuclear power plants and for the documents relating to the fire protection that are to be submitted to STUK (Finnish Radiation and Nuclear Safety Authority). Inspections of the fire protection arrangements to be conducted by STUK during the construction and operation of the power plants are also described in this guide. The guide can also be followed at other nuclear facilities

  12. Academic training for nuclear power plant operators

    International Nuclear Information System (INIS)

    After having briefly outlined the importance of academic training of nuclear power plant operators and the objectives of such a training (quality, addressing industry needs), the author evokes the programs implemented at the Center for Nuclear Studies of the Memphis State university. He notices that an academic degree is necessary for the recognition of the operator's job as a professional, and that such a training program is useful to improve safety and reliability of nuclear power plants

  13. Sensor network for nuclear power plant

    International Nuclear Information System (INIS)

    This study proposes an innovative method for the monitoring the nuclear power plant. In this field, false detection of the trouble, both 'false negative' and 'false positive' will become a serious problem. In the other hand, since its complexity of nuclear power plant, simplicity of monitoring system is strongly required. Here, we propose new method of signal processing and data transmission to realize reliable monitoring system consisted of multiple nodes of sensors. (author)

  14. Quality assurance organization for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides requirements, recommendations and illustrative examples for structuring, staffing and documenting the organizations that perform activities affecting quality of a nuclear power plant. It also provides guidance on control of organization interfaces, and establishment of lines for direction, communication and co-ordination. The provisions of this Guide are applicable to all organizations participating in any of the constituent areas of activities affecting quality of a nuclear power plant, such as design, manufacture, construction, commissioning and operation

  15. Exergy efficiency graphs for thermal power plants

    International Nuclear Information System (INIS)

    Despite the strong support for exergy in thermodynamics, the industry still relies on energy based power plant efficiencies. The paper exposes errors with energy based efficiencies and improves the graphical representation of plants efficiencies. Among others, energy efficiencies cannot recognised that Combined Heat and Power (CHP) plant may be less efficient than condensing plants or that fossil fuel based plants should always be more efficient than any biomass plants because irreversibilities from biomass spontaneous thermo-chemical reactions are much higher than with coal or natural gas. Profitability equations fail to distinguish the true technical efficiency so exergy must be used, if only to enhance power plants understanding. Two novel graphs are introduced. Graph #1 combines all in a single graph; total, electrical and thermal exergy efficiencies. Graph #2 splits thermal exergy efficiency into two components related to; plant thermal losses and useful heat output quality. Data from 24 existing and design plants is used to support the graphs. Graph #1 shows different rankings of efficiencies than what is typically understood by the industry. Graph #2 shows that achieving further higher thermal energy efficiency barely increases the total exergy efficiency. If possible, it is better to increase the useful heat output quality. - Highlights: • Paper identifies weaknesses of industrial approach for power plant efficiencies. • Two exergy efficiency graphs are introduced to improve graphical representation. • Graph 1 combines electrical, thermal and total exergy efficiencies. • Graph 2 splits thermal exergy efficiency into its energy efficiency and useful heat output quality. • Graphs use typical data from 24 power plants of various technologies and fuels

  16. Intelligent distributed control for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-01-01

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

  17. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

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

  18. Market Integration of Virtual Power Plants

    DEFF Research Database (Denmark)

    Petersen, Mette Kirschmeyer

    Global efforts to reduce emissions of carbon dioxide drives the introduction of renewable power production technologies into the existing power system. The real-time balance between production and consumption must, however, still be maintained at all times. Unfortunately, this is becoming...... increasingly challenging due to the intrinsic variability of production technologies such as photovoltaics and wind turbines. In a Smart Grid system the balancing task will therefore be handled by mobilizing flexibility on the consumption side. This Thesis assumes that the Smart Grid should be commercially...... based rather than funded by subsidies. Consequently the Smart Grid provides a business opportunity for so-called Virtual Power Plants. A Virtual Power Plant is an independent commercial operator, which provides Smart Grid capabilities to flexible consumers. This means that the Virtual Power Plant is the...

  19. Simulation model of a PWR power plant

    International Nuclear Information System (INIS)

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

  20. OUT Success Stories: Solar Trough Power Plants

    Science.gov (United States)

    Jones, J.

    2000-08-01

    The Solar Electric Generating System (SEGS) plants use parabolic-trough solar collectors to capture the sun's energy and convert it to heat. The SEGS plants range in capacity from 13.8 to 80 MW, and they were constructed to meet Southern California Edison Company's periods of peak power demand.

  1. Parabolic Trough Organic Rankine Cycle Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Canada, S.; Cohen, G.; Cable, R.; Brosseau, D.; Price, H.

    2005-01-01

    Arizona Public Service (APS) is required to generate a portion of its electricity from solar resources in order to satisfy its obligation under the Arizona Environmental Portfolio Standard (EPS). In recent years, APS has installed and operates over 4.5 MWe of fixed, tracking, and concentrating photovoltaic systems to help meet the solar portion of this obligation and to develop an understanding of which solar technologies provide the best cost and performance to meet utility needs. During FY04, APS began construction of a 1-MWe parabolic trough concentrating solar power plant. This plant represents the first parabolic trough plant to begin construction since 1991. The plant will also be the first commercial deployment of the Solargenix parabolic trough collector technology developed under contract to the National Renewable Energy Laboratory (NREL). The plant will use an organic Rankine cycle (ORC) power plant, provided by Ormat. The ORC power plant is much simpler than a conventional steam Rankine cycle power plant and allows unattended operation of the facility.

  2. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  3. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  4. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  5. An introductory course to power plant operations using a full-function power plant simulator

    International Nuclear Information System (INIS)

    A two-course sequence has been developed to provide a detailed introduction to power plant systems and a meaningful hands-on experience operating a full-function power plant simulator. The first time the course was taught, a Westinghouse facility was used as the reference plant. The course is now designed to use a General Electric boiling water reactor (BWR)/6 facility as the reference plant and has been taught twice using the Perry Nuclear Power Plant Simulator Facility. The overall objective of this course is to provide a vehicle for students to integrate their theoretical course work into a fundamental and practical understanding of the purpose, design, and operation of power plant instrumentation, electrical, hydraulic, pneumatic, and power generation systems. Students are required to be in at least their second year of a graduate program. Students at this level have had most of the course work necessary to perform the operations analyses expected of new nuclear plant engineers

  6. Materials Investigation for Power Plants and Power Industry. Seminar

    International Nuclear Information System (INIS)

    The Report is an assembly of the papers concerning the present state and perspectives of evolution of power industry in Poland, in this the development of atomic energy. The material and diagnostic problems occurring the exploitation of power station as well as gas pipelines are also discussed. The progress in the accommodation of the Polish technical prescriptions to the European law is also described. (authors)

  7. Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    The lecture is divided into three parts: 1) the legal conception and requirements of the German Atomic Energy Law (with special view on construction and operation of nuclear power plants), 2) the role of the Federation ('Bund') and the 'Laender' in the field of atomic energy and the Radiation Protection Ordinance (especially for licensing and supervision of nuclear power plants), 3) the function, participants, types and sequence of the strongly formalised licensing procedure for nuclear power plants, technical assessment in the frame of this procedure, content of a licence, possibility for altering the licence at a later date, role of administrative courts, continual supervision. (orig./HP)

  8. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, providing maintenance facilities and equipment, procuring stores and spare parts, selecting and training maintenance personnel, reviewing and controlling plant modifications arising from maintenance, and for generating, collecting and retaining maintenance records. Maintenance shall be subject to quality assurance in all aspects important to safety. Because quality assurance has been dealt with in detail in other Safety Guides, it is only included here in specific instances where emphasis is required. Maintenance is considered to include functional and performance testing of plant, surveillance and in-service inspection, where these are necessary either to support other maintenance activities or to ensure continuing capability of structures, systems and components important to safety to perform their intended functions

  9. Commissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The basic objective of commissioning programs is to demonstrate that systems will operate as designed. This involves testing under conditions which simulate normal, upset and accident conditions. Experience with commissioning of plants supports the current commissioning practices and suggests improvements that should be made

  10. Advanced nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Full text: Korea Hydro and Nuclear Power Co., Ltd (KHNP) is the largest power company among the six subsidiaries that separated from Korea Electric Power Corporation (KEPCO) in 2001, accounting for approximately 25% of electricity producing facilities, hydro and nuclear combined. KHNP operates 20 nuclear power plants in Kori, Yonggwang, Ulchin and Wolsong site and several hydroelectric power generation facilities, providing approximately 36% of the national power supply. As a major source of electricity generation in Korea, nuclear energy contributes greatly to the stability of national electricity supply and energy security. KHNP's commercial nuclear power plant operation, which started with Kori Unit 1 in 1978, has achieved an average capacity factor more than 90% since 2000 and a high record of 93.4% in 2008. Following the introduction of nuclear power plants in the 1970's, Korea accumulated its nuclear technology in the 1980's, developed OPR 1000(Optimized Power Reactor) and demonstrated advanced level of its nuclear technology capabilities in the 2000's by developing an advanced type reactor, APR 1400(Advanced Power Reactor) which is being constructed at Shin-Kori Unit 3 and 4 for the first time. By 2022, KHNP will construct additional 12 nuclear power plants in order to ensure a stable power supply according to the Government Plan of Long-Term Electricity supply and Demand. 4 units of OPR 1000 reactor model will be commissioned by 2013 and 8 units of APR 1400 are under construction and planned. At the end of 2022, the nuclear capacity will reach 33% share of total generation capacity in Korea and account for 48% of national power generation. (author)

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

    International Nuclear Information System (INIS)

    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

  12. Artificial intelligence in nuclear power plants. Vol. 2

    International Nuclear Information System (INIS)

    The IAEA Specialists' Meeting on Artificial Intelligence in Nuclear Power Plants was arranged in Helsinki/Vantaa, Finland, on October 10-12, 1989, under auspices of the International Working Group of Nuclear Power Plant Control and Instrumentation of the International Atomic Energy Agency (IAEA/IWG NPPCI). Technical Research Centre of Finland together with Imatran Voima Oy and Teollisuuden Voima Oy answered for the practical arrangements of the meeting. 105 participants from 17 countries and 2 international organizations took part in the meeting and 58 papers were submitted for presentation. These papers gave a comprehensive picture of the recent status and further trends in applying the rapidly developing techniques of and safety in designing and using of nuclear power worldwide

  13. Questions and Answers About Nuclear Power Plants.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC.

    This pamphlet is designed to answer many of the questions that have arisen about nuclear power plants and the environment. It is organized into a question and answer format, with the questions taken from those most often asked by the public. Topics include regulation of nuclear power sources, potential dangers to people's health, whether nuclear…

  14. Selection procedures for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Selection procedures in reference to experience in staffing two Wisconsin Electric Power Company nuclear project offices and the Point Beach Nuclear Power Plant are discussed. Wisconsin Electric has had a great deal of experience in the application of psychological tests and evaluation procedures, and it was natural that a major consideration in staffing these facilities was the selection of testing procedures

  15. Informatization of Power Plant and Its Implementation

    Institute of Scientific and Technical Information of China (English)

    Zhang Zhenghai

    2006-01-01

    @@ This paper presents the working procedure of power generating enterprises and explains the framework of an e-power-plant and its information system, puts forward the guideline and the general goal of informatization construction while focusing on the construction goal in the applied system, the implementing strategy, the project management and organization.

  16. Harmonic Resonances in Wind Power Plants

    DEFF Research Database (Denmark)

    Fernandez, Francisco Daniel Freijedo; Chaudhary, Sanjay; Teodorescu, Remus;

    2015-01-01

    This work reviews the state-of-the-art in the field of harmonic resonance problems in Wind Power Plants (WPPs). Firstly, a generic WPP is modeled according to the equivalent circuits of its passive and active components. Main focus is put on modeling active components, i.e. the ones based on power...

  17. Natural Circulation Performance in Nuclear Power Plants

    International Nuclear Information System (INIS)

    The present paper deals with a study of natural circulation in PWR systems, The study consists of two parts: in the first one, natural circulation in experimental facilities simulating PWR plants was analyzed. This made it possible to gather a broad data base which was assumed as a reference for the subsequent part of the research. Seven Nuclear Power Plants nodalizations and additional experimental data from ''non-PWR'' facilities have been considered in the second part of the paper. Conclusions are drawn about natural circulation capabilities derived for the seven Nuclear Power Plants nodalizations and from data base pertinent to three ''non-PWR'' facilities. (author)

  18. Natural circulation performance in nuclear power plants

    International Nuclear Information System (INIS)

    The present paper deals with a study of natural circulation in PWR systems. The study consists of two parts: in the first one, natural circulation in experimental facilities simulating PWR plants was analysed. This made it possible to gather a broad data base which was assumed as a reference for the subsequent part of the research. Seven Nuclear Power Plants nodalization and additional experimental data from 'non-PWR' facilities have been considered in the second part of the paper. Conclusions are drawn about natural circulation capabilities derived for the seven Nuclear Power Plants nodalization and from data base pertinent to three 'non-PWR' facilities. (author)

  19. Methods of assessing nuclear power plant risks

    International Nuclear Information System (INIS)

    The concept of safety evalution is based on safety criteria -standards or set qualitative values of parameters and indices used in designing nuclear power plants, incorporating demands on the quality of equipment and operation of the plant, its siting and technical means for achieving nuclear safety. The concepts are presented of basic and optimal risk values. Factors are summed up indispensable for the evaluation of the nuclear power plant risk and the present world trend of evaluation based on probability is discussed. (J.C.)

  20. Requirements of safety for future nuclear power plants

    International Nuclear Information System (INIS)

    Presently, about 450 different nuclear power plants, partly highly developed, are operating worldwide. Thereby, a great contribution to the worldwide current supply is made by nuclear energy. With a capacity amounting to 360 GWel, these nuclear plants meet 17% of the total energy demand. The use of nuclear energy will become more and more important on a longterm basis, if attention is paid to aspects of resource saving, economic efficiency and care of the environment, with special regard to the reduction of CO2 emissions. This, however, requires high safety demands concerning the operation of plants, the intermediate storage and the final storage. Several approaches regarding the safety aspects of future nuclear plants are pursued today. The new safety quality has to ensure that radioactive fission products remain within the reactor plant in any case of failure and thus no catastrophic consequences can occur outside the plant. This is for instance provided by the modified German Atomic Law (1994). In the following account, the safety concept and the possibilities of nuclear core meltdown so far as well as their consequences are discussed. Based on this, the safety demands for future power stations are defined and put in concrete terms. Some examples of solutions that have already been realised and which meet the requirement of being without any risk of catastrophe are presented in the following. Having discussed the different concepts of realising a core reactor with new safety requirements, details concerning the proof of the safety behaviour of future nuclear power stations are explained. (orig.)

  1. Cooling water requirements and nuclear power plants

    International Nuclear Information System (INIS)

    Indian nuclear power programme is poised to scuttle the energy crisis of our time by proposing joint ventures for large power plants. Large fossil/nuclear power plants (NPPs) rely upon water for cooling and are therefore located near coastal areas. The amount of water a power station uses and consumes depends on the cooling technology used. Depending on the cooling technology utilized, per megawatt existing NPPs use and consume more water (by a factor of 1.25) than power stations using other fuel sources. In this context the distinction between 'use' and 'consume' of water is important. All power stations do consume some of the water they use; this is generally lost as evaporation. Cooling systems are basically of two types; Closed cycle and Once-through, of the two systems, the closed cycle uses about 2-3% of the water volumes used by the once-through system. Generally, water used for power plant cooling is chemically altered for purposes of extending the useful life of equipment and to ensure efficient operation. The used chemicals effluent will be added to the cooling water discharge. Thus water quality impacts on power plants vary significantly, from one electricity generating technology to another. In light of massive expansion of nuclear power programme there is a need to develop new ecofriendly cooling water technologies. Seawater cooling towers (SCT) could be a viable option for power plants. SCTs can be utilized with the proper selection of materials, coatings and can achieve long service life. Among the concerns raised about the development of a nuclear power industry, the amount of water consumed by nuclear power plants compared with other power stations is of relevance in light of the warming surface seawater temperatures. A 1000 MW power plant uses per day ∼800 ML/MW in once through cooling system; while SCT use 27 ML/MW. With the advent of new marine materials and concrete compositions SCT can be constructed for efficient operation. However, the

  2. Licensing issues in the context of terrorist attacks on nuclear power plants

    International Nuclear Information System (INIS)

    The terrorist attack on the World Trade Center in September 2001 has prompted enhanced nuclear risk awareness among the German population. But in the current public debate about the safety of nuclear power plants in Germany in times of new dimensions of danger, aspects such as the role of the constitutional law, the German Atomic Energy Act, and the regulatory system governing nuclear power plant licensing in the context of protection and safety have not been addressed. The author therefore discusses the German nuclear power plant licensing law and administrative regime, elaborating on the significance attributed in those bodies of law to risks like terrorist attacks on nuclear power plants. (orig./CB)

  3. Safety Assessment - Swedish Nuclear Power Plants

    International Nuclear Information System (INIS)

    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

  4. 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.

  5. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  6. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

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

  7. Population distribution around Bushehr nuclear power plant

    International Nuclear Information System (INIS)

    Population distribution around the nuclear power plant is one of the most important factors to be considered. For the Bushehr nuclear power plant, information on current population distribution in the external zone up to a 80 kilometer radius in the vicinity of the site is collected. Also a projection of population for the plant lifetime has been made. Finally, the collected data was classified according to the age and sex. For this purpose, the area around the power plant was divided into concentric rings, and the rings were divided into 16 sectors. The population from 366 villages and 5 towns are about 328,000 inhabitants. In this survey, the population for 1985 was prepared on the basis of the 1977 census, and the results are indicated on the figures and tables. The above information will be used in evaluation of the potential radiological impact of normal and accidental releases, planning of emergency measures, and calculation of individual and collective doses

  8. Construction plan of Sendai Nuclear Power Plant

    International Nuclear Information System (INIS)

    In the Sendai nuclear power station, the construction of Unit 1 was started in January, 1979, to start the operation from July, 1984, and that of Unit 2 in May, 1981, to start the operation from March, 1986. Both plants are of PWR type, each with 890 MWe. In the design of the PWR plant, the national improved standard PWR model, as well as the experiences with existing LWR plants are fully incorporated. The purpose is to raise the reliability and safety, to improve the operation and maintenance and to reduce personnel radiation exposure. First, the siting and construction process of the nuclear power station is explained. Then, the features of the reactor power plants are described as follows: aseismic design, condensers, turbines, steam generators, reactor protection, reactor vessels, etc. (J.P.N.)

  9. Th-100 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Steenkampskraal Thorium Limited (STL) is a private company which is designing, marketing, licensing and commercializing a 100MWt thorium fueled pebble bed reactor. The concept plant design has been completed and work on the basic design has started. First site to determine the fuel cycle employed. Strong emphasis is placed on modular construction to reduce costs. STL hopes to start the licensing process within the next 6-8 months

  10. Nuclear power plants: safety management, safety culture

    International Nuclear Information System (INIS)

    The meeting on Nuclear Power Plants: Safety Management, Safety Culture held in Munich on October 30-31, 2002 has made very important contributions to the exchange of ideas and to the analysis of the current situation with respect to this topic. Eighteen technical papers were presented in which the subject was treated and put up for discussion under a variety of aspects raised by nuclear power plant operators, regulatory authorities, expert consultants, experts, scientists, and consultants. The findings elaborated at the event will greatly help to strengthen safety further in electricity generation from nuclear power at its current high level. (orig.)

  11. Market integration of Virtual Power Plants

    DEFF Research Database (Denmark)

    Petersen, Mette Kirschmeyer; Hansen, Lars Henrik; Bendtsen, Jan Dimon;

    2013-01-01

    We consider a direct control Virtual Power Plant, which is given the task of maximizing the profit of a portfolio of flexible consumers by trading flexibility in Energy Markets. Spot price optimization has been quite intensively researched in Smart Grid literature lately. In this work, however, we...... develop a three stage market model, which includes Day-Ahead (Spot), Intra-Day and Regulating Power Markets. This allows us to test the hypothesis that the Virtual Power Plant can generate additional profit by trading across several markets. We find that even though profits do increase as more markets are...

  12. Safety principles for nuclear power plants

    International Nuclear Information System (INIS)

    The role and purpose of safety principles for nuclear power plants are discussed. A brief information is presented on safety objectives as given in the INSAG documents. The possible linkage is discussed between the two mentioned elements of nuclear safety and safety culture. Safety culture is a rather new concept and there is more than one interpretation of the definition given by INSAG. The defence in depth is defined by INSAG as a fundamental principle of safety technology of nuclear power. Discussed is the overall strategy for safety measures, and features of nuclear power plants provided by the defence-in-depth concept. (Z.S.) 7 refs

  13. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Joaquim F. de [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)], E-mail: jfdc35@uol.com.br; Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)], E-mail: illsauer@iee.usp.br

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority.

  14. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    De Carvalho, Joaquim F. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)]|[Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority. (author)

  15. Integration of torrefaction with steam power plant

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-09-01

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

  16. Monitoring Biological Activity at Geothermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Peter Pryfogle

    2005-09-01

    The economic impact of microbial growth in geothermal power plants has been estimated to be as high as $500,000 annually for a 100 MWe plant. Many methods are available to monitor biological activity at these facilities; however, very few plants have any on-line monitoring program in place. Metal coupon, selective culturing (MPN), total organic carbon (TOC), adenosine triphosphate (ATP), respirometry, phospholipid fatty acid (PLFA), and denaturing gradient gel electrophoresis (DGGE) characterizations have been conducted using water samples collected from geothermal plants located in California and Utah. In addition, the on-line performance of a commercial electrochemical monitor, the BIoGEORGE?, has been evaluated during extended deployments at geothermal facilities. This report provides a review of these techniques, presents data on their application from laboratory and field studies, and discusses their value in characterizing and monitoring biological activities at geothermal power plants.

  17. Performance analysis of OTEC power plant

    International Nuclear Information System (INIS)

    The energy is the basis for almost all industrial activities and domestic needs. But recently there are increasing concerns internationally over environmental problems and consequent climate changes caused by the excessive use of fossil fuels. Furthermore the price of crude oil is increasing steadily with unstable supplies. In order to solve these national energy problems, the utilization of ocean energy is introduced as one of the best alternative technologies for the future. OTEC power plant has been installed at the west Inchon power plant site. Temperature differences of 20∼25 deg. C have been utilized for plant operations, where R22 is used as a working fluid. The system is composed of low pressure turbine, plate type heat exchanger, and pumps. In the present investigation the experimental results, such as gross power, net power and objective function, are analysed when temperature differences change from the reference design point

  18. Decentralised electrical distribution network in power plants

    International Nuclear Information System (INIS)

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

  19. Intelligent operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power plants consist of many systems and are operated by skillful operators with plenty of knowledge and experience of nuclear plants. Recently, plant automation or computerized operator support systems have come to be utilized, but the synthetic judgment of plant operation and management remains as human roles. Toshiba is of the opinion that the activities (planning, operation and maintenance) should be integrated, and man-machine interface should be human-friendly. We have begun to develop the intelligent operation system aiming at reducing the operator's role within the fundamental judgment through the use of artificial intelligence. (author)

  20. Nuclear power plants in Europe 1990

    International Nuclear Information System (INIS)

    In 1989 the nuclear power plants in operation in the twelve countries of the European Community produced 589.8 TWh, which is 35.6% of the total net electricity generation of 1655.8 TWh. Of the European countries, France has the highest share of nuclear power in (net) electricity generation, i.e., 74.6% and 288.7 TWh. The nuclear power plants in Belgium produced 39 TWh, thus contributing 60.8% to the total net electricity generation. In the Federal Republic of Germany, the electricity generation in nuclear power plants rose by 2.8% in 1989 over the level of 1988, attaining 149.5 TWh, which marks roughly 39.5% of the public electricity supply. In Spain, nuclear power plants produced 56.1 TWh, which means a contribution of 38.4% to the total net electricity generation. In Hungary, 13.9 TWh were converted from nuclear power into electricity in 1989, thus achieving 47.5% of the total electricity generation in the country. In Britain, the share of nuclear power in the total net electricity generation was 63.4 TWh or 21.7%, in the Netherlands 3.8 TWh or 5.4%. (orig.)

  1. Development of nuclear power plant technology in Russia

    International Nuclear Information System (INIS)

    Up to its disintegration the Soviet Union was one of the leading nuclear powers in the world. This also applied to the peaceful uses of nuclear energy. The broad spectrum of developments in nuclear power plant technology is astounding. Three reactor lines were developed and built independently: the VVER pressurized water reactor line up to VVER-1000 (water-water power reactor); the graphite-moderated RBMK boiling water reactor line up to RBMK-1500 (high-power reactor with channels), and the sodium cooled fast breeder reactors up to BN-600. The associated scientific installations and the nuclear machine building industry were mainly concentrated in Russia and remained there as a core capability in nuclear power plant technology also after the end of the Soviet Union. The current lines of small, medium-sized and large reactors under development, designed for construction in Russia proper and for exports, are presented in the article. Alongside technical developments, Russia rearranged the economic capacities of her nuclear industry so as to be able to meet her objectives in building nuclear power plants in the country and abroad. The main parts of the nuclear industry are combined in the 'AtomEnergoProm' holding. (orig.)

  2. 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

  3. Nuclear Power Plant Management Processes for Indian HWRs

    International Nuclear Information System (INIS)

    The Indian government, in response to the Fukushima accident, through the words of the Honourable Prime Minister of India, took the position that the safety of nuclear power plants is a matter of the highest priority for the country and consequently ordered safety audits of all operating nuclear power plants as well as those under construction. Major findings of the assessment of plants by utilities were that the existing nuclear power plants’ designs meet regulatory requirements for externally initiated events. They are in a position to ensure core cooling in the absence of off-site and on-site power supplies, and they have on-site water storage for decay heat removal. There are procedures to handle external events, loss of UHS and station blackout. In addition, vulnerabilities to extreme beyond design events were identified and in response, to further enhance safety, the auditors recommended incorporating automatic reactor trips in all nuclear power plants for seismic events, and to strengthen provisions for beyond design basis accidents. In addition, they provided means for augmentation of on-site water supplies, provided smaller diesel generator sets for charging batteries and running small capacity pumps, and incorporated extra provisions to enhance containment safety and fuel pool safety and to formalize and implement severe accident management guidelines. In terms of external event assessments, the auditor recommended that plants review the magnitude of postulated design basis natural events and the related requirements for siting and design of nuclear power plants as specified in the Atomic Energy Regulatory Board (AERB) safety regulations, which are appropriate and sufficiently conservative. However, in light of the Fukushima experience, it is prudent to further enhance this conservatism and also postulate beyond design basis natural events

  4. 76 FR 78702 - Progress Energy Florida, Inc. (Combined License Application for Levy County Nuclear Power Plant...

    Science.gov (United States)

    2011-12-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Progress Energy Florida, Inc. (Combined License Application for Levy County Nuclear Power Plant, Units 1 and 2) Notice of Atomic Safety and Licensing Board Reconstitution Pursuant to 10 CFR 2.313(c) and 2.321(b), the Atomic Safety and...

  5. The Oil-Fired MHD Power Plant

    International Nuclear Information System (INIS)

    It has been shown in an earlier paper what thermal efficiencies can be hoped for from a combined MHD-steam power station for different fuels, seeding, magnetic field strength, etc. However, a large pilot-plant is required to prove the intrinsic reliability of the MHD-power station, and also its probable competitiveness with a conventional power station. In this paper a possible pilot plant, a heavy-fuel-oil-fired MHD-steam power station is described. Residual fuel oil has been steadily increasing in significance in European power station practice over the past few decades. The MHD pilot plant must be as simple as possible in concept, so that the question of its reliability can be answered. The two essential unknowns are the designs of the MHD duct and the large superconducting magnets. Both preheating of the air above about 800°C and oxygen enrichment should be dispensed with for the time being. The combustion chamber should be constructed according to well-proved principles. It is proposed as well-that the seeding problem should be simply handled. In the example discussed, it seems possible that the specific plant costs of the whole power station will be kept to the level prevailing for steam power stations of the same output, while the thermal efficiency, after taking into account all the losses which can at the moment be assessed, is still 15% higher than that of the regular power station. If only the proposed pilot plant is considered, then the enormous development costs for the high temperature preheater and other costly items can be postponed until a later date, when the further development of the open cycle MHD-power station can be fully justified. (author)

  6. Nuclear power plant security assessment technical manual.

    Energy Technology Data Exchange (ETDEWEB)

    O' Connor, Sharon L.; Whitehead, Donnie Wayne; Potter, Claude S., III

    2007-09-01

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  7. Nuclear power plant security assessment technical manual

    International Nuclear Information System (INIS)

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  8. 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

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Cliffs Nuclear Power Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant... for light-water nuclear power reactors,'' which requires that the calculated emergency core...

  9. Water processing in power plants

    International Nuclear Information System (INIS)

    Surface water can be treated to a high degree of efficiency by means of new compact processes. The quantity of chemicals to be dosed can easily be adjusted to the raw water composition by intentional energy supply via agitators. In-line coagulations is a new filtration process for reducing organic substances as well as colloids present in surface water. The content of organic substances can be monitored by measuring the plugging index. Advanced ion-exchanger processes (fluidised-bed, compound fluidised-bed and continuously operating ion exchanger plants) allow the required quantity of chemicals as well as the plant's own water consumption to be reduced, thus minimising the adverse effect on the environment. The reverse-osmosis process is becoming more and more significant due to the low adverse effect on the environment and the given possibilities of automation. As not only ionogenic substances but also organic matter are removed by reverse osmosis, this process is particularly suited for treating surface water to be used as boiler feed water. The process of vacuum degassing has become significant for the cold removal of oxygen. (orig.)

  10. Joint Arab project for building of nuclear power plants

    International Nuclear Information System (INIS)

    Recently many Arab countries have expressed their interest in adopting nuclear power for electricity generation and seawater desalination in their energy strategies and hence sought assistance from IAEA and Arab Atomic Energy Agency. The Council of the League of Arab States at the summit level encouraged member states to develop peaceful use of atomic energy in different aspects of development, especially in energy generation and to establish a cooperative Arab program in this field. The burden of infrastructure can be reduced significantly if an Arab country forms a sharing partnership with other Arab countries. The sharing can be between two or more Arab states. It can include physical facilities, common programmes and knowledge, which will reflect in economic benefits. The sharing can also contribute in a significant manner to harmonization of codes and standards in general and regulatory framework in particular. This article outlines the major direct benefits of joint nuclear Arab programme to build a Nuclear Power Plants. (author)

  11. Power plant perspectives for sugarcane mills

    International Nuclear Information System (INIS)

    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 CO2 emissions, and increasing economic and social benefits.

  12. A BWR power plant simulator for Barsebaeck

    International Nuclear Information System (INIS)

    A computer simulator of a Barsebaeck power plant unit has been developed in cooperation between Sydkraft AB, Lund Institute of Technology, and Risoe National Laboratory. The simulator is of the kind often referred to as a compact simulator, because it involves only a computer with display screens and other input/output devices plus the software needed for calculation and presentation of the plant state as a function of time, and no sort of model of the control room as in large reactor simulators for operator training. The purpose of training courses with the compact simulator is to give students a better understanding of the behaviour of the power plant under transient conditions by displaying variables, e.g. pressures, temperatures, reactivity, nuclear power, as functions of time, thereby showing the interactions between different parts of the plant during the transient and the influence of a number of possible operator actions. The present paper describes the Barsebaeck compact simulator with the emphasis on the software developed at Risoe National Laboratory. The Risoe work comprises the programming of the dynamic plant model, in the form of a number of Fortran subroutines containing the physical description of the power plant. (author)

  13. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  14. Nuclear Security for Floating Nuclear Power Plants

    International Nuclear Information System (INIS)

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  15. Nuclear power plants 1985 - a world survey

    International Nuclear Information System (INIS)

    The Quick Statistics annually compiled by atw lists 355 nuclear power plants with 263,027 gross MWe in operation in 26 countries in late 1985. Another 163 units with 157801 MWe were under construction in 25 countries, and 75 units with 77,328 MWe were ordered in 18 countries. This adds up to a total of 593 units with an aggregate 498,156 MWe. In the course of 1985 30 nuclear generating units with 28,375 MWe were newly commissioned in 17 countries and 33 units in 14 countries started commercial operation. In the survey of electricity generation in 1985 for which no information was made available from the Eastern block countries, a total of 289 nuclear power plants were covered. In the year under review they generated an aggregate 1,270,854 GWh, which is 18.4% less than in the previous year. The highest nuclear generation again was recorded in the USA with 404,515 GWh, followed by France with 24,644 GWh. The KWG Grohnde Nuclear Power Station in the Federal Republic of Germany attained the maximum annual production figure of 1,477 GWh. The survey includes 10 tables indicating the generating performance of each nuclear power plant, the development of electricity generation in nuclear plants, and status of, nuclear power plants at the end of 1985 arranged by countries, types of reactors, and reactor manufacturers. (orig.)

  16. Nuclear power plants 1995 - a world survey

    International Nuclear Information System (INIS)

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

  17. The assessment of the environmental external costs of power plants for both coal-fired plant and nuclear power plant

    International Nuclear Information System (INIS)

    Efforts were made to assess the environmental external costs of power plants for both Samchonpo coal-fired plant and Younggwang nuclear power plant by using the computer program developed by the IAEA. In the case that the emission control devices such as precipitator for particulates reduction, wet scrubber for SO2, and low-NOx burner for NOx were installed in the coal-fired power plant, total environmental external cost was estimated as 33.97Won/kWh, much higher than 0.76Won/kWh of Younggwang nuclear power plant. And this study also assessed and compared the environmental external costs when Younggwang nuclear power plant was replaced by the coal-fired power plant at the same site and with the same capacity. According to the result, total environmental external cost of coal-fired power plant, with the emisison control devices installed, was estimated as 792 million US$ and it was about 50 times higher than 15 million US$ of Younggwang nuclear power plant. Although the result of this study had some limits due to using the simplified model, it was still true that nuclear power was much more environmentally friendly power source than coal-fired power

  18. Technology and costs for dismantling a Swedish nuclear power plant

    International Nuclear Information System (INIS)

    Various estimates concerning the costs of decommissioning a redundant nuclear power reactor to the green fields state are given in the literature. The purpose of this study is to provide background material for the Swedish nuclear power utilities to estimate the costs and time required to dismantle an ASEA-ATOM Boiling Water Reactor. The units Oskarshamn II and Barsebeck 1, both with an installed capacity of approximately 600 MW, serve as reference plants. The time of operation before final shutdown is assumed to be 40 years. Dismantling operations are initiated one year after shutdown. When the dismantling of the plant is finished, the site is to be released for unrestricted use. The costs for dismantling and subsequent final disposal of the radioactive waste are estimated at approximately SEK 500 million (approximately US dollars 120 million) in terms of 1979 prices. The sum includes 25% contingency. The dismantling cost is equivalent to 10-15% of the installation cost of an equivalent new nuclear power plant. The exact percentage is dependent on the interest rate during the construction period. It is shown in the study that a total dismantling can be accomplished in less than five years. This report is a compilation of studies performed by ASEA-ATOM and VBB based on premises given by KBS. The reports from these studies are presented in appendices. (Auth.)

  19. Insurance risk of nuclear power plant concentrations

    International Nuclear Information System (INIS)

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

  20. Nuclear power plants, citizens' action groups, power of state

    International Nuclear Information System (INIS)

    If you follow the scientific discussion on the pros and cons of the peaceful utilization of nuclear energy (obviously only suicides agree on its non-peaceful utilization) you can state the following two tendencies at first sight: Scientists do only deal with this problem to strengthen hypotheses they have already made. In most cases they deal with a system which is characterized by a lack of calculations, an even greater lack of tests and by a lot of speculation. Advocates of nuclear power plants like to join in this argumentation. Only few scientists question the abstract model of calculation on the burden caused by nuclear power plants, showing that a larger radioactive burden may trigger an uncontrolable, complex reaction within the body (as e.g. Contergan did). In the following we discuss in outline form a few aspects to be considered by operators of nuclear power plants. (orig./GL)

  1. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  2. Efficiency improvement of thermal coal power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hourfar, D. [VEBA Kraftwerke Ruhr Ag, Gelsenkirchen (Germany)

    1996-12-31

    The discussion concerning an increase of the natural greenhouse effect by anthropogenic changes in the composition of the atmosphere has increased over the past years. The greenhouse effect has become an issue of worldwide debate. Carbon dioxide is the most serious emission of the greenhouse gases. Fossil-fired power plants have in the recent past been responsible for almost 30 % of the total CO{sub 2} emissions in Germany. Against this background the paper will describe the present development of CO{sub 2} emissions from power stations and present actual and future opportunities for CO{sub 2} reduction. The significance attached to hard coal as one of today`s prime sources of energy with the largest reserves worldwide, and, consequently, its importance for use in power generation, is certain to increase in the years to come. The further development of conventional power plant technology, therefore, is vital, and must be carried out on the basis of proven operational experience. The main incentive behind the development work completed so far has been, and continues to be, the achievement of cost reductions and environmental benefits in the generation of electricity by increasing plant efficiency, and this means that, in both the short and the long term, power plants with improved conventional technology will be used for environmentally acceptable coal-fired power generation.

  3. Essays on the economics of licensing nuclear power plants

    International Nuclear Information System (INIS)

    Regulation and licensing of nuclear power plants by the United States Atomic Energy Commission and the United States Nuclear Regulatory Commission are discussed. Chapter 1 overviews the licensing process and issues raised in licensing cases. Based on a sample of plants licensed between 1967 and 1978, a statistical study of the impact of public participation in licensing is performed. The study concludes that public participation has had a major impact on licensing and power-plant costs. The impact is due to a fundamental weakness of the Commissions: their inability to resolve certain issues related to acceptable social risk. The study has important policy implications for reforming the Federal licensing process. Chapter 2 contains an analysis of the Price-Anderson Act, a Federal program for compensating victims of large nuclear accidents. The Price-Anderson Act is placed within the context of generalized federal disaster relief. A model is developed that allows an evaluation programs on the basis of moral hazard and equity principles. Chapter 3 analyzes the Nuclear Regulatory Commission's treatment of its mandatory antitrust review of applicants for nuclear power plants. The main conclusion of the chapter is that the reviews have not addressed the central economic issues of antitrust that are relevant to nuclear power. Instead, the reviews contribute to further cartelization of the electric utility industry. While politically expedient, the reviews are counter-productive to the development of an optimal industry structure

  4. Safety aspects of operation of nuclear power plants. Results achieved

    International Nuclear Information System (INIS)

    Three main factors are discussed which affect the safety of nuclear power plant operation in Czechoslovak conditions. In order to assure the quality of components important for nuclear safety and to maintain it throughout their service life, the Czechoslovak Atomic Energy Commission issued a Decree in 1979 whose essence was in that already the safety report should identity components with a view to nuclear safety. Individual programmes of quality assurance are then drawn up for these components. At present, an amendment is being prepared for the Decree. The second factor is the quality of operating personnel of all categories, and especially of the so-called selected categories. In 1979 a unified system was introduced of nuclear power plant personnel training. Since 1984 the training institution has been provided with a full-size simulator. The third factor is the quality of the operation management of the facility, especially as concerns the observance of limits and conditions of safe operation. The respective document has been available for V-213 reactors since 1982, for V-230 units of the V-1 nuclear power plant in Jaslovske Bohunice since 1988. A system has been introduced of data collection, evaluation and distribution relating to failures in Czechoslovak nuclear power plants, based on IAEA recommendations. It has a very low threshold for reporting failures so that on average some 80 failures are reported for every operating unit. (Z.M.)

  5. Nuclear Mpd Gas Turbine Power Plant

    International Nuclear Information System (INIS)

    In MPD generators employing alkali-metal-seeded inert gases as the working fluid, the possibility of utilizing magnetically-induced non-equilibrium ionization has been established on theoretical grounds and there is supporting experimental evidence. Joule heating of the working plasma preferentially enhances the electron temperature, producing plasma electrical conductivity levels much higher than apply for thermal equilibrium ionization. The effect is increased by increasing the applied magnetic field and (within limits) by reducing the operating pressure level. If high levels of electrical conductivity can be maintained in this non-equilibrium mode, a cycle in which temperature levels are dictated on thermodynamic grounds only can be selected. The optimization of a Brayton cycle in terms of thermodynamic efficiency and specific power is considered. The proposed cycle consists simply of a heat source, MPD generator, recuperator, heat sink and compressor, the latter being driven either electrically or by a turbine in the circuit. The general features of a land-based nuclear, recuperative closed-cycle MPD power plant are presented. An all-graphite prismatic core helium-cooled nuclear reactor is the heat source. A single gas thermodynamic cycle is considered rather than combined gas and steam cycles, to avoid the hazards of water-graphite reactions due to in-leakage from a high pressure steam cycle and to simplify the plant and its control. The detailed plant layout-suggested is given theoretical and practical justification. Detailed parametric surveys on the MPD generator and the cycle thermodynamics have been performed and some of the combined results are presented. With a reactor outlet temperature of 1800°K, gas turbine inlet temperature of 1200°K, single intercooling and cycle losses estimated from present technological data, it is shown that net plant efficiencies of 55-60% can be obtained. Fuel temperatures for a range of reactor and fuel geometries, reactor

  6. Nuclear power/water pumping-up composite power plant

    International Nuclear Information System (INIS)

    In a nuclear power/water pumping-up composite power plant, a reversible pump for pumping-up power generation connected to a steam turbine is connected to an upper water reservoir and a lower water reservoir. A pumping-up steam turbine for driving the turbine power generator, a hydraulic pump for driving water power generator by water flowing from the upper water reservoir and a steam turbine for driving the pumping-up pump by steams from a nuclear reactor are disposed. When power demand is small during night, the steam turbine is rotated by steams of the reactor, to pump up the water in the lower water reservoir to the upper water reservoir by the reversible pump. Upon peak of power demand during day time, power is generated by the steams of the reactor, as well as the reversible pump is rotated by the flowing water from the upper water reservoir to conduct hydraulic power generation. Alternatively, hydraulic power generation is conducted by flowing water from the upper reservoir. Since the number of energy conversion steps in the combination of nuclear power generation and pumping-up power generation is reduced, energy loss is reduced and utilization efficiency can be improved. (N.H.)

  7. Feedwater heater life optimization at Peach Bottom Atomic Power Station

    International Nuclear Information System (INIS)

    Many papers published over the last 15 years have strongly emphasized the need for an ongoing program of inspection and testing with subsequent failure cause analysis of feedwater heaters. With deregulation of the electric utility industry in various phases of implementation, utilities must decrease costs, both O ampersand M and capital, while optimizing plant efficiency. In order to accomplish this coal, utility engineers must monitor feedwater heater performance in order to recognize degradation, correct/eliminate failure mechanisms, and prevent in-service failures while optimizing availability. Periodic tube plugging without complete analysis of the degraded/failed area resolves the immediate need for return for service, however, heater life will not be graded/failed area resolves optimized. This paper illustrates a complete inspection, testing, and maintenance program implemented at PECO Energy's Peach Bottom Atomic Power Station (PBAPS). Concerns that tubes may have been too conservatively plugged due to insufficient data justified a program that included: (1) Removal of previously installed plugs. (2) Videoprobe inspection of failed areas. (3) Extraction of tube samples for further analysis. (4) Eddy current testing of selected tubes. (5) Evaluation of the condition of open-quotes insuranceclose quotes plugged tubes for return to service. (6) Hydrostatic testing of selected tubes. (7) Final repair plan based on the results of the above program. This paper concludes that no single method of inspection or testing should solely be relied upon in establishing: (1) The extent of actual degraded conditions, (2) The source(s) of failure mechanisms, (3) The details of repair. It is a combination of all gathered data that affords the best chance in arresting problems and optimizing feedwater heater life

  8. Nuclear power plants are getting movable

    International Nuclear Information System (INIS)

    Russia is building the first floating nuclear plant. This ship named 'Academic Lomonosov' is 144 meter long and 30 meter wide, it carries 2 compact reactors KCT-40S we find usually on ice-breakers and submarines (although the enrichment of their nuclear fuel will be lower), each one releases an electrical power of 35 MW, together they are sufficient to power a city of 200.000 inhabitants. The 'Academic Lomonosov' is scheduled to be operating in 2012 in the Kamchatka peninsula. Its cost rounds 230 millions euros and 6 similar floating plants are planned to be built in Russia till 2020. In order to comply with the non-proliferation treaty, the floating power plants will be rented to foreign operators but not sold. The Russian owner will stay in charge of the operating and maintenance works and of the complete nuclear fuel cycle. This project confirms the actual and general trend for smaller nuclear units. (A.C.)

  9. Nuclear power plant and state border

    International Nuclear Information System (INIS)

    The paper constitutes the slightly revised version of a legal opinion given to those local authorities in Germany which are affected by the construction of the Cattenom powerplant centre in France near to her borders with Germany and Luxembourg. In this opinion, especially claims were examined which might be raised by local authorities according to public and private law, or by the inhabitants of frontier areas, constituting, among other things, claims to the information required, to necessary measures to be taken for the safety of the population and for environmental protection, and ways and means of enforcing them. In addition, the power plant owner's civil liability for the damaging effects of power plant operation are examined as well as the international liability of the state which builds power plants. (HSCH)

  10. Ground acceleration in a nuclear power plant

    International Nuclear Information System (INIS)

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

  11. Hitachi's maintenance technologies for nuclear power plant

    International Nuclear Information System (INIS)

    Abstract of high maintenance technologies for nuclear power plants, the technologies for new inspection system, maintenance of in-core instruments and piping, and technologies for high output power of plants are stated. The high maintenance technologies aim at long-term stable operation, increase of capacity factor, and decrease of exposure. Some examples of maintenance technologies of in-core equipments and primary loop recirculation (PLR) piping such as stress improvement and repair work are explained. Hydrogen water chemistry (HWC) and noble metal chemical addition (NMCA) for corrosion are described. Abstract of maintenance technologies, execution of water jet peening (WJP), outline of equipments of induction heating stress improvement (IHSI), the outside appearance of remote operation vehicle (ROV), advanced vortex nozzle (AVN), continuous cover blade (CCB), combined intermediate valve (CIV), moisture separator and heater (MSH), and evaluation examples of high output power of plants are illustrated. (S.Y.)

  12. Environmental protection in thermal power plants

    International Nuclear Information System (INIS)

    This workbook is a compilation of the most important facts and data that are relevant today for environmental protection in thermal power plants. Unlike the other issues the text is not in the form of a random collection of data but in the form of a complete presentation. Possible elaboration projects for pupils can be easily derived from the individual sections. These deal with: the discussion about environmental protection; forest decline; sources of emission; nuisances in the Federal Republic of Germany; environmental protection in fossil-fuel power plants - clean air - cooling water utilization and water protection - noise; environmental protection in nuclear power plants - radioactive material produced in nuclear reactors and the retention of such materials - radioactive waste materials - monitoring of radioactive emissions; accessory materials and hints. (orig./HSCH)

  13. Customer benefit and power plant development

    International Nuclear Information System (INIS)

    In recent years, many aspects of the power market and customer needs in plant operation have been changing more rapidly than manufacturers could launch new products on the market. As a result, flexibility is required not only in the operation of power plants, but also in drawing up product specifications and in the ensuing engineering. The familiar major objectives of development work, such as low specific investment cost and high efficiency, remain important. Also in the context of reducing CO2 emissions and trading with CO2 certificates, improving the efficiency of power plants is a measure that, over and above today's cost optimum, represents the 'action of least regret' with a view to sustainably meeting the requirements of the Kyoto Protocol. (orig.)

  14. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole fourth quarter of 1991. The load factor average was 94.7 % (the whole year 90.9 %). All the events in the last annual quarter, which are classified on the International Nuclear Event Scale, were below scale/level 0. Also the events which occurred in the other quarters of the year 1991 were rated at the scale's lowest levels. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure originating in nuclear power plants were detected in the samples collected in the vicinity of the nuclear power plants

  15. Electronuclear power plants in future nuclear power production

    International Nuclear Information System (INIS)

    The article outlines several options for achieving the transmutation of long-lived radioactive wastes. A brief description of fast reactors and proton accelerators for this purpose is given. The article then describes several possible uses of electronuclear plants, consisting of a subcritical blanket with an external neutron source comprised of a linear proton accelerator and a neutron-producing target, for transmutation. Transmutation in electronuclear plants without energy consumption, with power production, and with power production as well as the production of new fissioning materials are all outlined. 11 refs

  16. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1997)

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1997 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1997; (4) Capital construction; (5) Nuclear safety; (6) Radiation safety; (7) Work safety and health protection at work; (9) Fire protection; (10) Units upgrading - safety measures; (11) Maintenance; (12) Operation; (13) Environmental impacts of operations; (14) List of balances; (15) Human sources; (16) International co-operation; (17) Public relations

  17. Bid invitation specifications for nuclear power plants

    International Nuclear Information System (INIS)

    The Guidebook on Bid Invitation Specifications for Nuclear Power Plants is primarily directed to the managers and senior professional staff of plant owner organizations intending to launch a call for bids for a first nuclear power plant. However, the Guidebook should also be of some value for experienced owners who are about to acquire a follow-up unit. The purpose of this Guidebook is to give advice on the kind of information to be provided by the prospective plant owner to the prospective suppliers. This information should enable them to have a clear conception of the owner's wishes, of his requirements and preferences, the conditions and circumstances under which the tasks should be performed, and the detailed data and information requested of them. The presentation of this information should be such that bid evaluation and contract negotiations are facilitated

  18. Fiber optic applications in nuclear power plants

    International Nuclear Information System (INIS)

    Fiber optic technology possesses many desirable attributes for applications in commercial nuclear power plants. The non-electrical nature of fiber optics is an important factor in an industry governed by federal safety regulations such as Class 1E isolation and separation criteria. Immunity from Electromagnetic Interference (EMI), an increasing industry problem area, is another significant characteristic. Because of the extremely wide bandwidth offered, fiber optics better addresses the data acquisition and communication requirements of the complex processes of a nuclear power plant. Potential for fiber optic sensor applications exists within the nuclear industry because their small size and physical flexibility allows access into normally inaccessible areas. They possess high accuracy and allow environmentally sensitive electronics to be remotely located. The purpose of this paper is to explore current applications for fiber optic technology in modern nuclear plants, document examples of present day usage in C-E plants and suggest possible future application areas

  19. Thermal power plant wastes and their management

    International Nuclear Information System (INIS)

    The problem of pollution caused by coal-fired thermal power plants is still of importance because of the tremendous growth in use of electrical energy. The wastewaters of a typical coal fired power plant include cooling tower blowdown, wastewaters from ash handling system, boiler blowdown, regenerate wastes, floor and yard drains, coal pile run off etc. The solid waste is the fly ash. The present communication deals with the physico-chemical characteristics of fly ash pond effluent and the fly ash and their effects on certain chemical properties of soil, seed germination pattern and the growth of some crop plants. The plants selected for these studies were as follows: for fly ash pond effluent - kidney bean (Phaseolus aureus) and lady's finger (Abelmoschus esculentus), whereas for the fly ash - wheat (Triticum aestivum) and pea (Pisum sativum). 7 tabs.; 20 refs. (author)

  20. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  1. Power plant conceptual studies in Europe

    International Nuclear Information System (INIS)

    The European Power Plant Conceptual Study (PPCS) has been a study of conceptual designs for commercial fusion power plants. It focussed on five power plant models, named PPCS A, B, AB, C and D, which are illustrative of a wider spectrum of possibilities. They are all based on the tokamak concept and they have approximately the same net electrical power output, 1500 MWe. These span a range from relatively near-term, based on limited technology and plasma physics extrapolations, to an advanced conception. All five PPCS plant models differ substantially from the models that formed the basis of earlier European studies. They also differ from one another, which lead to differences in economic performance and in the details of safety and environmental impacts. The main emphasis of the study was on system integration. Systems analyses were used to produce self-consistent plant parameter sets with approximately optimal economic characteristics for all models. In the PPCS models, the favourable, inherent, features of fusion have been exploited to provide substantial safety and environmental advantages. The broad features of the safety and environmental conclusions of previous studies have been confirmed and demonstrated with increased confidence. Two key innovative developments made within the PPCS study are worthy of a special note. One is the development of a scheme for the scheduled replacement of the internal components which shows the potential for an overall plant availability in excess of 75%. The other is a conceptual design for a helium-cooled divertor, which permits the toleration of heat loads of at least 10 MW/m2. The PPCS study has highlighted the need for specific design and R and D activities, in addition to those already underway within the European long term R and D programme, as well as the need to clarify the concept of DEMO, the device that will bridge the gap between ITER and the first-of-a-kind fusion power plant. (author)

  2. Operator training simulator for nuclear power plant

    International Nuclear Information System (INIS)

    In nuclear power plants, training of the operators is important. In Japan, presently there are two training centers, one is BWR operation training center at Okuma-cho, Fukushima Prefecture, and another the nuclear power generation training center in Tsuruga City, Fukui Prefecture, where the operators of PWR nuclear power plants are trained. This report describes the BWR operation training center briefly. Operation of a nuclear power plant is divided into three stages of start-up, steady state operation, and shut down. Start-up is divided into the cold-state start-up after the shut down for prolonged period due to periodical inspection or others and the hot-state start-up from stand-by condition after the shut down for a short time. In the cold-state start-up, the correction of reactivity change and the heating-up control to avoid excessive thermal stress to the primary system components are important. The BWR operation training center offers the next three courses, namely beginner's course, retraining course and specific training course. The training period is 12 weeks and the number of trainees is eight/course in the beginner's course. The simulator was manufactured by modeling No. 3 plant of Fukushima First Nuclear Power Station, Tokyo Electric Power Co. The simulator is composed of the mimic central control panel and the digital computer. The software system comprises the monitor to supervise the whole program execution, the logic model simulating the plant interlock system and the dynamic model simulating the plant physical phenomena. (Wakatsuki, Y.)

  3. A Tsunami Fragility Assessment for Nuclear Power Plants in Korea

    International Nuclear Information System (INIS)

    Although Tsunami events were defined as an external event in 'PRA Procedure Guide (NUREG/CR- 2300)'after 1982, a Tsunami event was not considered in a design and construction of NPP before the Sumatra earthquake in 2004. But the Madras Atomic Power Station, a commercial nuclear power plant owned and operated by the Nuclear Power Corporation of India Limited (NPCIL), and located near Chennai, India, was affected by the tsunami generated by the 2004 Sumatra earthquake (USNRC 2008). The condenser cooling pumps of Unit 2 of the installation were affected due to flooding of the pump house and subsequent submergence of the seawater pumps by tsunami waves. The turbine was tripped and the reactor shut down. The unit was brought to a cold-shutdown state, and the shutdown-cooling systems were reported as operating safely. After this event, Tsunami hazards were considered as one of the major natural disasters which can affect the safety of Nuclear Power Plants. The IAEA performed an Extrabudgetary project for Tsunami Hazard Assessment and finally an International Seismic Safety Center (ISSC) established in IAEA for protection from natural disasters like earthquake, tsunami etc. For this reason, a tsunami hazard assessment method determined in this study. At first, a procedure for tsunami hazard assessment method was established, and second target equipment and structures for investigation of Tsunami Hazard assessment were selected. Finally, a sample fragility calculation was performed for one of equipment in Nuclear Power Plant

  4. OPTIMIZING THE PERFORMANCE OF THERMAL POWER PLANTS

    OpenAIRE

    Sushila Mishra; Ganesh Chembedu

    2016-01-01

    Failure of boiler tubes has been a familiar phenomenon in power plants resulting in unscheduled plant shut down; in consequence, there are heavy losses in industrial production. The failure of boiler tubes appears in the form of bending, bulging, cracking, wearing or rupture, causing leakage of the tubes. The failure can be caused by one or more modes such as overheating, stress corrosion cracking (SCC), hydrogen embrittlement, creep, flame impingement, sulfide attack, weld attack, ash erosio...

  5. Nuclear power plant outage optimisation strategy

    International Nuclear Information System (INIS)

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

  6. Experience in operation of nuclear power plant

    International Nuclear Information System (INIS)

    Following a brief description of the structure, financing and generating plant of Sydkraft, the Barsebaeck plant is briefly described. The construction schedule and personnel are outlinrd as are the investment and operating costs, which are compared with the utility's oil-fired generating costs. The causes of outages are briefly presented and discussed. The wastes from generating the same amount of power as Barsebaeck in 1977 using oil fuel are compared with the radioactive waste for that year. (JIW)

  7. Seismic instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

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

  8. Site selection for new nuclear power plants

    International Nuclear Information System (INIS)

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  9. Site selection for new nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur, E-mail: paul.rizzo@rizzoassoc.com, E-mail: melissa.dubinsky@rizzoassoc.com, E-mail: onur.tastan@rizzoassoc.com [RIZZO Associates Inc., Pittsburgh, PA (United States); Miano, Sandra C., E-mail: scm27@psu.edu [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), RJ (Brazil); Pennsylvania State University, Department of Mechanical and Nuclear Engineering, State College, PA (United States)

    2015-07-01

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  10. The EU power plant conceptual study

    International Nuclear Information System (INIS)

    An integrated Power Plant Conceptual Study (PPCS) was launched in 1988 in the frame of the European Fusion Programme. The objective of the PPCS is to demonstrate: the credibility of fusion power plant design(s); the claims for the safety and environmental advantages and for the economic viability of fusion power. In addition results of the PPCS Programme will help to define the R and D Programme. The strategy of the PPCS is to study a limited number of Plant Models that span the expected range of possibilities. These range from an advanced version of International Thermonuclear Experimental Reactor (ITER) through to the presently foreseen ultimately achievable values of the plasma physics and technology parameters, together with a range of blanket and high heat flux technologies. The primary focus of detailed studies, and the first work to be undertaken, is on two Plant Models that emphasise limited extrapolation, since credibility within the philosophy of a possible fast-track development of fusion power is a major aim of the study. The remainder of this paper discusses the physics studies and the preliminary technology studies that have formed the launching pad for the detailed studies of Plant Models within the PPCS. The discussion concentrates on the 'limited extrapolation' Models that are being studied first, with brief reference to the Models that are further from ITER

  11. Exergy analysis of a cogeneration power plant

    International Nuclear Information System (INIS)

    In the following study exergetic evaluation of a cogeneration power plant in operation with installed electrical capacity of 24 MW and process heat demand of 190 MW it is performed. The main objective of the research was to determine the influence of the increase in power generation capacity, raising the superheated steam parameters and the number of regenerative heaters on the second law efficiency and irreversibilities in the different components of the plant. To study the power plant was divided into subsystems: steam generator blowdown expander, main steam pipe, steam turbine regenerative heaters, reduction system, deaerator and pumps. The study results show that exergy losses and irreversibilities differ widely from one subsystem to another. In general, the total irreversibility accounted for 70.7% of primary fuel availability. The steam generator subsystem had the highest contribution to the irreversibility of the plant by 54%. It was determined that the increased steam parameters helps reduce the irreversibility and increase the exergetic efficiency of installation. The suppression of the reduction and incorporation of extraction-condensing turbine produce the same effect and helps to reduce power consumption from the national grid. Based on the results recommendations for improving plant efficiency are made. (full text)

  12. VISIT - Virtual visits to nuclear power plants

    International Nuclear Information System (INIS)

    For more than twenty years, EDFs Communication Division has conducted a policy of opening its generation sites to the general public. Around 300,000 people visit a nuclear power plant every year. However, for the security of persons and the safety of facilities, those parts of the plant situated in controlled areas are not accessible to visitors. For the sake of transparency, EDF has taken an interest in the technologies offered by virtual reality to show the general public what a nuclear power plant is really like, so as to initiate dialogue on nuclear energy, particularly with young people. Visit has been developed with virtual reality technologies. It serves to show the invisible (voyage to the core of fission), the inaccessible and to immerse the visitors in environments which are usually closed to the general public (discovery of the controlled area of a nuclear power plant). Visit is used in Public Information Centres which receive visitors to EDF power plants and during international exhibitions and conferences. Visit allows a virtual tour of the following controlled areas: locker room hot area/cold area, a necessary passage before entering the controlled areas; reactor building; fuel building; waste auxiliary building (liquid, solid and gaseous effluents). It also includes a tour of the rooms or equipment usually accessible to the general public: control room, turbine hall, transformer, air cooling tower

  13. Ground assessment methods for nuclear power plant

    International Nuclear Information System (INIS)

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

  14. High power proton accelerator for nuclear power plant

    International Nuclear Information System (INIS)

    The novel nuclear power system--Energy Amplifier, proposed by C. Rubbia, attracts the interest as a prior option for the development of the next generation nuclear power plant in the first half of the 21st century. The accelerator used to drive the system should provide proton beam power tens higher than that of LAMPF. The accelerator physics and technology have been advancing greatly since LAPMF was built more than 20 years ago. These new progresses become the essential basis for the intense beam accelerator to advance up to a much higher beam power. However, some challenges are still being faced, including beam loss, high efficiency, reliability, as well as some technical issues associated with high power CW operation. The accelerator design options to tackle with the difficulties are discussed. The suggestions on R and D of high power accelerator in China are presented

  15. Development of concentrated solar power and conventional power plant hybrids

    OpenAIRE

    Suojanen, Suvi

    2016-01-01

    CSP hybrids are one of the possible technical solutions in order to increase the share of renewable energy and decrease greenhouse gas emission levels as well as fuel consump-tion. The main objectives of the thesis are to research state-of-the-art technologies in concentrated solar power (CSP) and conventional power plants, to comprehensively study the possible integration options and to develop one CSP hybrid configuration by using Advanced Process Simulator (Apros), which is a dynamic model...

  16. Virtual environments for nuclear power plant design

    Energy Technology Data Exchange (ETDEWEB)

    Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

    1996-03-01

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

  17. Nuclear Power Plant Temelin Technical Support Centre

    International Nuclear Information System (INIS)

    The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

  18. Nuclear power plant siting: Hydrogeologic aspects

    International Nuclear Information System (INIS)

    This Safety Guide gives guidelines and methods for determining the ground water concentration of radionuclides that could result from postulated releases from nuclear power plants. The Guide gives recommendations on the data to be collected and the investigations to be performed at various stages of nuclear power plant siting in relation to the various aspects of the movement of accidentally released radioactive material through the ground water, the selection of an appropriate mathematical or physical model for the hydrodynamic dispersion even two-phase distribution of the radioactive material and an appropriate monitoring programme

  19. Virtual environments for nuclear power plant design

    International Nuclear Information System (INIS)

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP)

  20. Decommissioning of nuclear power plants - safety aspects

    International Nuclear Information System (INIS)

    The stages of decommissioning a nuclear power plant are presented in popular form. There exist two alternatives: Safe containment of activated and highly contaminated components within the nuclear power plant unit or dismantling of all components and buildings. Stage 1 provides for safe containment in a) previously sealed buildings without any dismantling; b) containment resp. reactor building; c) underground structures. Stage 2 provides for partial dismantling with safe containment of the remaining parts a) within the biological shield, b) underground, after dismantling the parts above ground level. Stage 3 provides for total dismantling. (orig.)

  1. Diagnostic system for combine cycle power plant

    International Nuclear Information System (INIS)

    We developed the Diagnostic System for Combined Cycle Power Plant which enables inexperienced operators as well as experienced operators to cope with abnormal conditions of Combined Cycle Power Plant. The features of this system are the Estimate of Emergency Level for Operation and the Prediction of Subsequent Abnormality, adding to the Diagnosis of Cause and the Operation Guidance. Moreover in this system, Diagnosis of Cause was improved by using our original method and support screens can be displayed for educational means in normal condition as well. (Authors)

  2. Robotic fabrication and inspection for power plants

    International Nuclear Information System (INIS)

    The usage of Robotic Automation is now an integral part of the modern manufacturing systems. Applications in nuclear power plants is no exception. As a matter of fact, as a result of the hazards of radiations for the human workers makes automation of the on-site working highly desirable. This presentation will focus on the broad benefits by use of automation in Power plants. Various processes and technologies for robotic applications in fabrication, maintenance and inspection will be highlighted. The specific technology features for use in nuclear environments will be highlighted

  3. Site survey for nuclear power plants

    International Nuclear Information System (INIS)

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

  4. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

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

  5. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    During the second quarter of 1990 the Finnish nuclear plant units Loviisa 1 and 2 and TVO and II were in commercial operation for most of the time. The feedwater pipe rupture at Loviisa 1 and the resulting inspections and repairs at both Loviisa plant units brought about an outage the overall duration of which was 32 days. The annual maintenance outages of the TVO plant units were arranged during the report period and their combined duration was 31.5 days. Nuclear electricity accounted for 35.3% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 83.0%. Three events occurred during the report period which are classified as Level 1 on the International Nuclear Event Scale: feedwater pipe rupture at Loviisa 1, control rod withdrawal at TVO I in a test during an outage when the hydraulic scram system was rendered inoperable and erroneous fuel bundle transfers during control rod drives maintenance at TVO II. Other events during this quarter are classified as Level Zero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. Only small amounts of nuclides originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  6. Aging effects in PWR power plants components

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Diogo da S.; Guimaraes, Antonio C.F.; Moreira, Maria de Lourdes, E-mail: diogosb@outlook.com, E-mail: tony@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    This paper presents a contribution to the study of aging process of components in commercial plants of Pressurized Water Reactors (PWRs). The analysis is made through application of the Fault Trees Method, Monte Carlo Method and Fussell-Vesely Importance Measure. The approach of the study of aging in nuclear power plants, besides giving attention to the economic factors involved directly with the extent of their operational life, also provide significant data on security issues. The latest case involving process of life extension of a PWR could be seen in Angra 1 Nuclear Power Plant through investing of $27 million for the installation of a new reactor lid. The corrective action has generated an estimated operating life extension of Angra I in twenty years, offering great economy compared with building cost of a new plant and anterior decommissioning, if it had reached the time operating limit of forty years. The Extension of the operating life of a nuclear power plant must be accompanied by a special attention to the components of the systems and their aging process. After the application of the methodology (aging analysis of the injection system of the containment spray) proposed in this work, it can be seen that 'the increase in the rate of component failure, due the aging process, generates the increase in the general unavailability of the system that containing these basic components'. The final results obtained were as expected and may contribute to the maintenance policy, preventing premature aging process in Nuclear Plant Systems. (author)

  7. Aging effects in PWR power plants components

    International Nuclear Information System (INIS)

    This paper presents a contribution to the study of aging process of components in commercial plants of Pressurized Water Reactors (PWRs). The analysis is made through application of the Fault Trees Method, Monte Carlo Method and Fussell-Vesely Importance Measure. The approach of the study of aging in nuclear power plants, besides giving attention to the economic factors involved directly with the extent of their operational life, also provide significant data on security issues. The latest case involving process of life extension of a PWR could be seen in Angra 1 Nuclear Power Plant through investing of $27 million for the installation of a new reactor lid. The corrective action has generated an estimated operating life extension of Angra I in twenty years, offering great economy compared with building cost of a new plant and anterior decommissioning, if it had reached the time operating limit of forty years. The Extension of the operating life of a nuclear power plant must be accompanied by a special attention to the components of the systems and their aging process. After the application of the methodology (aging analysis of the injection system of the containment spray) proposed in this work, it can be seen that 'the increase in the rate of component failure, due the aging process, generates the increase in the general unavailability of the system that containing these basic components'. The final results obtained were as expected and may contribute to the maintenance policy, preventing premature aging process in Nuclear Plant Systems. (author)

  8. Nuclear power plant licence renewal - legal and policy issues

    International Nuclear Information System (INIS)

    Commercial nuclear power reactor operating licenses in the United States were issued for fixed terms, generally 40 years, subject to renewal. All but a few of the 118 plants expected to be licensed will reach the end of their license by the year 2030. The governing Federal statute, the Atomic Energy Act of 1954, does not prescribe specific safety standards for license renewal, so the Nuclear Regulatory Commission decided to issue its own standards through the exercise of its rulemaking power. This rulemaking is focusing on protection against possible age related degradation of plants and other safety questions relevant solely to extended operation, as opposed to broad re-reviews against current licensing standards. The rulemaking also includes a comprehensive review of the environmental impacts from extended operation of all 118 reactors which might be renewed. (author)

  9. Regulatory practices for nuclear power plants in India

    Indian Academy of Sciences (India)

    S S Bajaj

    2013-10-01

    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.

  10. Regulatory practices for nuclear power plants in India

    International Nuclear Information System (INIS)

    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)

  11. Development of robots for nuclear power plants

    International Nuclear Information System (INIS)

    In nuclear power plants, the reduction of maintenance time, the reduction of radiation exposure and man-power saving are increasingly required. To achieve these purposes, various remote-controlled devices, such as robots in a broad sense, have been earnestly developed. Of these, three machines for replacing, four devices for inspection, two systems for cleaning, and two equipment for processing are tabulated in this paper. Typical eight machines or equipment are briefly introduced, mainly describing their features or characteristics. Those are: a remotely handling machine for control rod drive mechanism, an automatic refueling machine, an automatic ultrasonic flaw detection system replacing for a manually operated testing system for the welded parts of primary cooling system, an automatic cask washing machine for decontamination, a floor-type remote inspection vehicle for various devices operating inside power plants, a monorail-type remote inspection vehicle for inspection in spaces where floor space is short, and a remote-controlled automatic pipe welding machine for welding operations in a radioactive environment such as replacing the piping of primary cooling system. Most of these devices serves for radiation exposure reduction at the same time. Existing nuclear power plant design assumes direct manual maintenance, which limits the introduction of robots. Future nuclear power plants should be designed on the assumption of automatic remote-controlled tools and devices being used in maintenance work. (Wakatsuki, Y.)

  12. Emissions from power plants 1988-1997

    International Nuclear Information System (INIS)

    The document gives statistics on the pollutive emissions from Danish power plants during the period 1988-1997, the main pollutants being sulphur dioxide, nitrogen oxides and carbon dioxide. Data on efficiency levels relative to the production of electricity and heating and on the power plants' contribution to the total emission of CO2, NOx, and SO2 from energy consumption in Denmark, are presented, and also as corrected for the net import of electricity. Other data on the emission of each of these chemicals by power plants are presented as factual, and corrected in accordance with the net import of electricity, and as factual per consumed and produced energy unit at the power plants. Short notes on related Danish legislation are found in addition to information on sources, methods and definitions used as a basis for the production of this document. Emission from power stations is dependent on their energy consumption which is in turn controlled by the demand for electricity and heating. It is stated that efforts to reduce emissions of sulphur dioxide, nitrogen oxides and carbon dioxide have led to a small reduction in air pollution by these chemicals during recent years. (AB)

  13. Nuclear power plant common aging terminology

    International Nuclear Information System (INIS)

    This report defines and encourages the use of a set of common terms and definitions that characterize aging and aging management of nuclear power plant systems, structures, and components. Common aging terminology encompasses the areas of degradation causes, degradation/aging, life, failure, and maintenance. The terminology should prove useful in plant license renewal, life-cycle management, maintenance, and equipment qualification. The principal intended benefits are improved reporting and interpretation of plant experience data (especially failure data) and improved interpretation and compliance with codes, standards, and regulations related to aging of nuclear power plants. The terminology was developed using a sound, systematic technical and lexicographical approach, as well as input from a committee with members from electric utilities, the Nuclear Management and Resources Council (NUMARC), the Electric Power Research Institute (EPRI), the United States Nuclear Regulatory Commission (NRC), and national research laboratories. Draft definitions received an extensive industry review. Formal comments were received from 19 organizations worldwide. The report presents the results of this effort and contains definitions, figures, examples of usage, dictionary definitions, and discussions describing the relationships among the 85 terms and 27 synonyms of the common aging terminology. The terms and definitions are generally consistent with similar terminology used by the Institute of Nuclear Power Operations (INPO). The common aging terminology has been reviewed by NUMARC and the NRC and is recommended for use throughout the nuclear power industry

  14. Nuclear power plant in whose backyard

    International Nuclear Information System (INIS)

    The authority to regulate the nuclear power industry resides largely with the federal government. But states have the responsibility to protect the health and safety of their citizens and to regulate land use within their borders. The siting of nuclear power plants can engender conflicts between these jurisdictions that are usually resolved in the courts. Most state challenges to federal control of nuclear power have been struck down or severely weakened by the preemption doctrine contained in the supremacy clause of Article VI of the Constitution, which provides for the preemption of federal law over state law in the event of direct conflict. The existing avenues for state control over siting and operation of nuclear power plants can be greatly strengthened while avoiding direct conflict with federal jurisdiction

  15. The earthquake security of the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    The seismic safety of Paks Nuclear Power Plant is analyzed. Assessment of earthquake risk has been done at the site of the plant, and seismic resistance of the nuclear power plant is analyzed together. (TRA)

  16. Alpha-nuclides in nuclear power plants

    International Nuclear Information System (INIS)

    The behaviour of alpha-nuclides in nuclear power plants is subject of the investigations presented. The source of alpha-nuclides is a contamination with fissile material (so called tramp uranium or tramp fuel) which deposits on fuel rod surfaces and leads to the build-up of transuranium nuclides. The determination of a defect situation with fuel release as well as the quantification of the fissile material contamination background is given for BWR and PWR plants. The quantification of the fuel release and the tramp uranium background can be calculated with different, measurable nuclides in BWR and PWR plants. (orig.)

  17. Accident Monitoring Systems for Nuclear Power Plants

    International Nuclear Information System (INIS)

    In the Fukushima Daiichi accident, the instrumentation provided for accident monitoring proved to be ineffective for a combination of reasons. The accident has highlighted the need to re-examine criteria for accident monitoring instrumentation. This publication covers all relevant aspects of accident monitoring in NPPs. The critical issues discussed reflect the lessons learned from the Fukushima Daiichi accident, involve accident management and accident monitoring strategies for nuclear power plants, selection of plant parameters for monitoring plant status, establishment of performance, design, qualification, display, and quality assurance criteria for designated accident monitoring instrumentation, and design and implementation considerations. Technology needs and techniques for accident monitoring instrumentation are also addressed

  18. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tubulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

  19. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hzard to the personnel or the environment

  20. Investment scenarios for Chinese power plants

    International Nuclear Information System (INIS)

    An analysis is provided of returns for investment in power plants in China and India. Three sample investment scenarios are compared to illustrate the relative merits of each financing arrangement. The best returns would seem to be offered by a mix of debt and equity financing. The potential problem of gradual currency depreciation can be overcome by early cash payments. Foreign investment in China's power generation industry would be more readily forthcoming if easier access to debt finance were available. (UK)

  1. Recirculation of Laser Power in an Atomic Fountain

    Science.gov (United States)

    Enzer, Daphna G.; Klipstein, WIlliam M.; Moore, James D.

    2007-01-01

    A new technique for laser-cooling atoms in a cesium atomic fountain frequency standard relies on recirculation of laser light through the atom-collection region of the fountain. The recirculation, accomplished by means of reflections from multiple fixed beam-splitter cubes, is such that each of two laser beams makes three passes. As described below, this recirculation scheme offers several advantages over prior designs, including simplification of the laser system, greater optical power throughput, fewer optical and electrical connections, and simplification of beam power balancing. A typical laser-cooled cesium fountain requires the use of six laser beams arranged as three orthogonal pairs of counter-propagating beams to decelerate the atoms and hold them in a three-dimensional optical trap in vacuum. Typically, these trapping/cooling beams are linearly polarized and are positioned and oriented so that (1) counter-propagating beams in each pair have opposite linear polarizations and (2) three of the six orthogonal beams have the sum of their propagation directions pointing up, while the other three have the sum of their propagation directions pointing down. In a typical prior design, two lasers are used - one to generate the three "up" beams, the other to generate the three "down" beams. For this purpose, the output of each laser is split three ways, then the resulting six beams are delivered to the vacuum system, independently of each other, via optical fibers. The present recirculating design also requires two lasers, but the beams are not split before delivery. Instead, only one "up" beam and one oppositely polarized "down" beam are delivered to the vacuum system, and each of these beams is sent through the collection region three times. The polarization of each beam on each pass through the collection region is set up to yield the same combination of polarization and propagation directions as described above. In comparison with the prior design, the present

  2. Energy investment in nuclear power plants

    International Nuclear Information System (INIS)

    The energy investment in terms of electrical and thermal energy requirements for nuclear power plants is examined. The total lifetime energy inputs required for a 1000-MW(e) plant based on a 30-year plant lifetime and 0.75 plant factor are presented for several pressurized-water-reactor (PWR) and boiling-water-reactor (BWR) systems, two high-temperature gas-cooled reactor (HTGR) systems, and one heavy-water-reactor (HWR) system. The energy analyses reviewed here have demonstrated that the energy expenditures for the various reactor systems are very much less than the energy produced by the reactors and that the initial energy investments are recovered in a short time after startup--several months to 2 years. The energy requirements associated with the individual processes, such as mining, enrichment, construction, and waste disposal, are tabulated for two different fuel cycles for a PWR and a BWR. The enriching process is by far the largest component of the electrical requirements, representing 85 to 90% of the total electrical energy investment. The energy used in constructing and operating the reactor constitutes the largest single investment of thermal energy, representing 50% of the total thermal energy requirements. Results of several analyses are examined and comparisons made between nuclear power plants, a coal plant, and a solar thermal-conversion plant

  3. Safer design for a nuclear power plant

    International Nuclear Information System (INIS)

    During the regulatory process for the issuing of the construction permit and the operating licence of the first Austrian nuclear power plant, more than 1200 injunctions have been issued for increasing its safety standard. In principle they belong to three groups: quality assurance and quality control; the improvement of the design; and probabilistic issues. Examples of all these three groups are given. When discussions with the parties in the regulatory process on the issuing of the operating licence were going on, work at the nuclear power plant was suddenly terminated following the negative outcome of a referendum. The main content of the discussions was that the nuclear inspectors keep permanent control over the plant and have a permanent record of occurrences there, that participation of the regulatory body is included in all issues which might influence the safety standard of the plant, and that the regulatory body may issue new injunctions on the operation of the plant if new standards arise from backfitting ensuing from lessons learned, from the treatment of generic issues, from new rules and regulations and from reactor safety research. Special attention is given to the process of mothballing the plant as was necessary after the referendum. The work on the plant was terminated in an orderly way; a final report was issued which stated what still would have to be done at the plant in order to go into operation. The mothballing began by demounting some systems, emptying others and shutting down a third group. Some ventilation systems are in operation. These activities are also recorded in reports; these, together with a final report of the status reached, could be the basis for revitalization work. Finally it is shown how Austria, with its limited means in terms of funds and personnel, is dealing with the problems of keeping the safety standard of the plant as high as at the plants in other countries with more funds and personnel available. (author)

  4. Control method for BWR type power plant

    International Nuclear Information System (INIS)

    The present invention provides a method of controlling a BWR type plant having internal pumps capable of sufficiently utilizing the performance of a whole volume turbine bypass plant to enable stable supply of electric power upon load interruption of power generator thereof. Namely, upon occurrence of load interruption of a power generator or turbine trip, a plurality of internal pumps are tripped simultaneously to abruptly reduce a reactor core flow rate by a predetermined value or more. In this case, a reactor core flow rate abruptly reduction scram signal is prevented. Alternatively, a plurality of internal pumps are tripped simultaneously to abruptly reduce the reactor core flow rate. In this case, a reactor core flow rate abrupt reduction scram set value is changed in order to inhibit the reactor core flow rate abrupt reduction scram signal. With such procedures, upon load interruption of power generator or upon trip of turbine, reactor core flow rate is abruptly reduced by trip of internal pumps for avoiding increase of neutron fluxes due to reactor pressure change. However, since reactor scram is avoided, the operation can be continued upon load interruption of power generator. As a result, performance of whole volume turbine bypass plant can be utilized sufficiently even upon occurrence of load interruption of power generator. (I.S.)

  5. Institutional approach to power plant safety culture

    International Nuclear Information System (INIS)

    The thesis of this paper is that the requirements for safety culture in nuclear power plants can be failing to recognize contradictions in the various pressures on the organization that have to be balanced in an optimal manner. Nuclear power plants are influenced by pressures from both external and internal sources, that can be viewed as comprising the two main institutionalizing influences on the organization. Most of the effort on safety culture definition and implementation has addressed the utility and the power plant, producing definitions of good practices and of hindrances to good utility safety culture. These often lack formal representation of the demands of the organization and of its environment that are related to institutional processes rather than to productivity. This paper adopts an institutional approach to organizations as a way of clarifying the nature of the interfaces between the power plant and its external agencies, and their respective safety culture requirements. The plant must respond to its own internal organizational demands that are both technical, related to efficiency and productivity, and institutionalizing in terms of organizational processes. External agencies create environmental demands that are primatily institutionalizing in nature, such as the legitimate requirements of society as represented by the regulatory body ; standards of practice desctibed by professional groups; or obligation to conform to international commitments. These inputs mu st be cognizant of all of the parameters of the plant's functioning if they are not to risk detracting from plant efficiency, and so safety. This is a measure of the safety culture of these external agencies. The utility's safety culture is dependent on its abi1ity to balance external demands , internal processes and technical imperatives. (author)

  6. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    During the first 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. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

  7. Risks of potential accidents of nuclear power plants in Europe

    OpenAIRE

    Slaper H; Eggink GJ; Blaauboer RO

    1993-01-01

    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed on an integrated assessment of probabilistic cancer mortality risks due to possible accidental releases from the European nuclear power plants. For each of the European nuclear power plants the prob...

  8. Recent advances in nuclear power plant simulation

    International Nuclear Information System (INIS)

    The field of industrial simulation has experienced very significant progress in recent years, and power plant simulation in particular has been an extremely active area. Improvements may be recorded in practically all simulator subsystems. In Europe, the construction of new full- or optimized-scope nuclear power plant simulators during the middle 1990's has been remarkable intense. In fact, it is possible to identify a distinct simulator generation, which constitutes a new de facto simulation standard. Thomson Training and Simulation has taken part in these developments by designing, building, and validation several of these new simulators for Dutch, German and French nuclear power plants. Their characteristics are discussed in this paper. The following main trends may be identified: Process modeling is clearly evolving towards obtaining engineering-grade performance, even under the added constraints of real-time operation and a very wide range of operating conditions to be covered; Massive use of modern graphic user interfaces (GUI) ensures an unprecedented flexibility and user-friendliness for the Instructor Station; The massive use of GUIs also allows the development of Trainee Stations (TS), which significantly enhance the in-depth training value of the simulators; The development of powerful Software Development Environments (SDE) enables the simulator maintenance teams to keep abreast of modifications carried out in the reference plants; Finally, simulator maintenance and its compliance with simulator fidelity requirements are greatly enhanced by integrated Configuration Management Systems (CMS). In conclusion, the power plant simulation field has attained a strong level of maturity, which benefits its approximately forty years of service to the power generation industry. (author)

  9. 76 FR 39908 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-07-07

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2.... DPR-53 and DPR-69, for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP), respectively... (ISFSI), currently held by Calvert Cliffs Nuclear Power Plant, LLC as owner and licensed...

  10. 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

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Regulatory Commission (the Commission) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC... Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and...

  11. CANDU 9 nuclear power plant simulator

    International Nuclear Information System (INIS)

    Simulators are playing, an important role in the design and operations of CANDU reactors. They are used to analyze operating procedures under standard and upset conditions. The CANDU 9 nuclear power plant simulator is a low fidelity, near full scope capability simulator. It is designed to play an integral part in the design and verification of the control centre mock-up located in the AECL design office. It will also provide CANDU plant process dynamic data to the plant display system (PDS), distributed control system (DCS) and to the mock-up panel devices. The simulator model employs dynamic mathematical models of the various process and control components that make up a nuclear power plant. It provides the flexibility to add, remove or update user supplied component models. A block oriented process input is provided with the simulator. Individual blocks which represent independent algorithms of the model are linked together to generate the required overall plant model. As a design tool the simulator will be used for control strategy development, human factors studies (information access, readability, graphical display design, operability), analysis of overall plant control performance, tuning estimates for major control loops and commissioning strategy development. As a design evaluation tool, the simulator will be used to perform routine and non-routine procedures, practice 'what if' scenarios for operational strategy development, practice malfunction recovery procedures and verify human factors activities. This paper will describe the CANDU 9 plant simulator and demonstrate its implementation and proposed utility as a tool in the control system and control centre design of a CANDU 9 nuclear power plant. (author). 2 figs

  12. Technical evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    In continuation of its efforts to provide comprehensive and impartial guidance to Member States facing the need to introduce nuclear power, the International Atomic Energy Agency is issuing this guidebook as part of a series of guidebooks and codes of practice and, in particular, as a necessary supplement to 'Economic Evaluation of Bids for Nuclear Power Plants: A Guidebook', published by the IAEA in 1976 as Technical Reports Series No.175. The present publication is intended for project managers and senior engineers of electric utilities who are concerned with the evaluation of bids for a nuclear power project. It assumes that the reader has a good knowledge of the technical characteristics of nuclear power plants and of nuclear power project implementation. Its purpose is to provide the information necessary to organize, guide and supervise the technical evaluation of bids for a nuclear power project. It goes without saying that the technical staff carrying out the evaluation must have prior technical experience which cannot be provided by a guidebook

  13. Electrochemical Power Plant for Terrestrial Flight Platforms Project

    Data.gov (United States)

    National Aeronautics and Space Administration — An electrochemical power plant is proposed by MicroCell Technologies to provide power to terrestrial flight platforms. Our power plant is based upon a proton...

  14. Restarting delayed nuclear power plant projects

    International Nuclear Information System (INIS)

    The management of nuclear power plant projects with delays of several years with respect to the original scheduled commercial operation date presents particular issues and problem areas beyond the normal management tasks needed for projects implemented within originally planned schedules. During the years 1997-1998 the IAEA collected information and practical examples on necessary management actions to preserve the capability for resuming work and completing delayed nuclear power projects when conditions permit. The results were published in the IAEA-TECDOC-1110 entitled Management of Delayed Nuclear Power Plant Projects. As this publication was finalized, at the end of 1998, the available information at the IAEA PRIS (Power Reactor Information System) indicated that more than 40 nuclear power plant projects had delays of five or more years with respect to the originally scheduled operation dates. The PRIS data, collected at the end of 2007, illustrates a trend toward restarting and completing projects that were once delayed. The data indicates that the number of delayed nuclear power projects has reduced to about 25. Some practical methodologies and successful experience from the restarted projects were reviewed, summarized and included in the present publication. The purpose is to address the specific management issues pertaining to a delayed nuclear power project in the period after the decision for restarting is adopted. This publication covers those management issues not considered within the normal processes described in other IAEA publications. It is expected that the practical experience collected from delayed nuclear power projects that were successfully restarted, completed and brought to commercial operation, can provide useful assistance to the management of similar projects considering resumption of work in the future. This publication was produced within the IAEA programme directed to increase the capability of Member States for strengthening national

  15. The site of a nuclear power plant and environmental safety

    International Nuclear Information System (INIS)

    guidelines concerning nuclear power plant safety and in the guides of the Radiation and Nuclear Safety Authority (STUK). International Atomic Energy Agency (IAEA) has published the Safety Standard concerning the site selection. There are two nuclear power plant sites in Finland; Olkiluoto in Eurajoki municipality and Haestholmen in the town of Loviisa; both of these are also proposed for the site of a new nuclear power plant unit in the application for decision in principle submitted to the Council of State by Teollisuuden Voima Oy (TVO). The Finnish sites are located on the coast, but in other countries there are also inland sites. The surroundings of the Finnish sites are relatively sparsely populated compared with e.g. the sites in USA and in Germany. Concerning external initial events, Finland is calm area, e.g. bedrock is stable and severe weather phenomena are not occurring. Persons and their organisations participating in the design, building and operation of a nuclear power plant as well as controlling these activities have an essential role in creating, maintaining and development of safety. Thus particular attention is paid to their ability and operational preconditions as well as to the quality control methods and safety culture of their organisations. The safety of the plant is based partly on design basis, according to which the plant shall survive in a sufficient way from incidents and accidents. Design bases include internal events of the power plant and external events such as flood, earthquake and crash of an aeroplane. The power plant is aimed to be constructed in such a way that it would not be damaged in an accident to such extent that radioactive material would be released to the environment. Applying appropriate rescue or radiation protection measures such as local sheltering, iodine tablets and evacuation can mitigate offsite damages possibly followed by the release caused by an accident. In addition to deterministic analyses accomplished to prove out

  16. Site preparation and excavation for foundation of power plant in construction works for No.2 plant in Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    Japan Atomic Power Co. has completed the improved Calderhall type power station in 1966, BWR type No.1 plant in Tsuruga Power Station in 1970, and the BWR type plant in Tokai No.2 Power Station in 1978. Now, as the fourth nuclear power plant, No.2 plant with 1160 MW output in Tsuruga Power Station is a PWR plant, and a prestressed concrete containment vessel was adopted for the first time in Japan. The site of No.2 plant is the limited area between No.1 plant and the Fugen Power Station, in which only the structures of the power plant can be placed, but there was no space for the temporary structure for construction works and abandoning earth. In excavation, the amount of special explosive was limited to avoid the effect of vibration and flying stones. The geological features of the site were examined by various tests. The outline of the civil engineering works is explained. The area of the site is 71,000 m2, and its level is EL + 7.0m. The amount of excavation is 770,000 m3. The excavation for the foundations of three main buildings amounts to 570,000 m3, and the amount of concrete is 17,500 m3. The method of excavation was selected according to the class of rocks. The excavation works were completed without trouble, and the construction is in progress smoothly. (Kako, I.)

  17. Atom for peace, code for war. The technology policy of the atomic power solution in Finland between 1955-1970

    International Nuclear Information System (INIS)

    explanation is given that the parallel, independent and nearly identical tenders reflected a post-war ideological rivalry between the state-owned utility Imatran Voima and private energy utilities. A private sector nuclear power association Voimayhdistys Ydin represented energy intensive paper and pulp industries and wanted to have free choice instead of being associated themselves with 'the state monopoly' in energy pricing. As a background to this, a decisive change had started to happen within Finnish energy policy: private and municipal big thermal power plants became incorporated into the national hydro power production system. A characteristic phenomenon in the later history is the Soviet Union s effort to bid for the tender of Imatran Voima. A nuclear superpower was willing to take part in competition but not on a turnkey basis as Imatran Voima had presumed. As a result of many political turns and four years of negotiations the first Finnish commercial light water reactor was ordered from the East. Soon after this the private nuclear power group ordered its reactors from Sweden. This work interprets this as a reasonable geopolitical balance in choosing politically sensitive technology. Conceptually, social and political dimensions of new technology are emphasised. Negotiations on the Finnish atomic energy program are viewed as a cooperation and a struggle, where state-oriented and private-oriented regimes pose their own macro level views and goals (technopolitical imaginaries) and defend and advance their plans and practical modes of action (schemata). Here, not only technologists but even political actors are seen to contribute to technopolitical realisations. (orig.)

  18. Safety assessment of emergency power systems for nuclear power plants

    International Nuclear Information System (INIS)

    This publication is intended to assist the safety assessor within a regulatory body, or one working as a consultant, in assessing the safety of a given design of the emergency power systems (EPS) for a nuclear power plant. The present publication refers closely to the NUSS Safety Guide 50-SG-D7 (Rev. 1), Emergency Power Systems at Nuclear Power Plants. It covers therefore exactly the same technical subject as that Safety Guide. In view of its objective, however, it attempts to help in the evaluation of possible technical solutions which are intended to fulfill the safety requirements. Section 2 clarifies the scope further by giving an outline of the assessment steps in the licensing process. After a general outline of the assessment process in relation to the licensing of a nuclear power plant, the publication is divided into two parts. First, all safety issues are presented in the form of questions that have to be answered in order for the assessor to be confident of a safe design. The second part presents the same topics in tabulated form, listing the required documentation which the assessor has to consult and those international and national technical standards pertinent to the topics. An extensive reference list provides information on standards. 1 tab

  19. The Daya Bay nuclear power plant

    International Nuclear Information System (INIS)

    The Daya Bay plant is nearing completion for the Guangdong Nuclear Power Joint Venture Company (GNPJVC), formed by the Chinese Government (75%) in conjunction with China Light Power, the Hong Kong utility (25%). 70% of generated power from two French-design 900 MWe class PWRs will be supplied to Hong Kong (the reference units: France's Gravelines-5 and -6). The Advanced Fuel Assembly designed by Framatome is used. The turbines are British-built (GEC) and designed differently from those installed in French units. 1 fig

  20. Problems facing a first nuclear power plant

    International Nuclear Information System (INIS)

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

  1. Elk and plants thrive near power lines

    Energy Technology Data Exchange (ETDEWEB)

    Lustre, L.

    1997-11-01

    Butterflies and elk gather in clearings near power line right-of-ways and on the edges of such clearings, where the wild flowers and plants that have widely disappeared as a result of intensive farming and subsurface drainage of fields have found a good habitat. Ornamental coniferous trees, various herbs and assorted berries do well and can be harvested near power lines from woodland clearings once thought unfit for cultivation. IVS, the nationwide network company, takes part in many projects aiming both to increase productive utilization of land areas under power lines and to promote biodiversity

  2. Medium-size power plants. Economic options

    International Nuclear Information System (INIS)

    In this paper the authors describe a method for economic evaluation of a nuclear power plant project such as advocated by the IAEA but modified through the introduction of various parameters that may affect the evaluation, i.e. the weighted evaluation rate, the annual increase in the cost of fuel, and the discount rate. The method is applied to barge-based medium-size reactors (125 MW(e)). The authors calculate the investment cost, together with the costs of administration, operation and maintenance; use is made of current assumptions regarding the price of fuel for the case of a reference nuclear plant and an oil-fired plant of the same power and in the same programme. In this way the authors derive the discounted cost of the nuclear programme and concurrent conventional programme on the basis of the following assumptions: a weighted inflation rate varying between 0 and 6% per year; an annual increase in real fuel prices ranging from 0 to 3%; and a real discount rate, equal to the real interest rate, varying between 4 and 7% per year and corresponding to nominal discount rates of up to 13.4%. The conclusion reached is that, given the real interest rates actually prevailing on the financial market, a weighted inflation rate foreseen by the majority of experts, and a rise in real fuel prices of the order of 1% per year, the medium-size nuclear power plant is more economical than a conventional plant of the same output. (author)

  3. Reliability improvement method for BWR power plants

    International Nuclear Information System (INIS)

    The construction of the nuclear power generating facilities in Japan was commenced by the import of technological know-how from the United States, but in ten years since then, they reached the stage of improvement and standardization by the effort for the domestic production and the accumulated technological ability. But the unscheduled stop of operation was not able to avoid centering around the initially imported plants, and it cannot be said that the sufficient rate of operation was attained. In Japan, plant manufacturers deliver the whole installations including nuclear reactors in the lump, and carry out the planning, design, manufacture, construction, periodic inspection and maintenance, accordingly the feedback of the operational results can be made quickly, differing from the U.S. system. As the result, No. 1 plant of the Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc., which was constructed by the domestic technology, has attained about 72% of the average rate of operation in six years, and showed the high reliability of the domestically produced plants. The measures for improving system reliability in system planning and the reliability of machinery and equipments, the method of evaluating the reliability of systems, machines and equipments, the quality of nuclear power generating facilities and the quality assurance, and the management of maintenance in Hitachi Ltd. are explained. (Kako, I.)

  4. Geothermal Cogeneration: Iceland's Nesjavellir Power Plant

    Science.gov (United States)

    Rosen, Edward M.

    2008-01-01

    Energy use in Iceland (population 283,000) is higher per capita than in any other country in the world. Some 53.2% of the energy is geothermal, which supplies electricity as well as heated water to swimming pools, fish farms, snow melting, greenhouses, and space heating. The Nesjavellir Power Plant is a major geothermal facility, supplying both…

  5. Utility-Scale Solar Photovoltaic Power Plants

    OpenAIRE

    International Finance Corporation

    2015-01-01

    With an installed capacity greater than 137 gigawatts (GWs) worldwide and annual additions of about 40 GWs in recent years, solar photovoltaic (PV) technology has become an increasingly important energy supply option. A substantial decline in the cost of solar PV power plants (80 percent reduction since 2008) has improved solar PV’s competitiveness, reducing the needs for subsidies and ena...

  6. Citizen participation in power plant siting

    Energy Technology Data Exchange (ETDEWEB)

    Ducsik, D.W.

    1981-04-01

    With continuing public concern for environmental consequences in the siting of large power plants, direct citizen participation in site selection is increasingly suggested as a means of resolving conflict. The relative merits of open planning strategy are discussed. Six basic concerns utility companies often cite about the practical implications of collaboration with environmentalists and other groups are explained.

  7. Environmental effects of thermal power plants

    International Nuclear Information System (INIS)

    Reviewing critically the present literature, the effects of thermal power plants on the environment are studied. At first, the loads of the different power plant types are compiled. With regard to the effects of emission reduction proceedings the pollutant emissions are quantified. The second chapter shows the effects on the ecological factors, which could be caused by the most important emission components of thermal power plants. Where it is possible, relations between immissions respectively depositions and their effects on climate, man, flora, fauna and materials will be given. This shows that many effects depend strongly on the local landscape, climate and use of natural resources. Therefore, it appears efficient to ascertain different load limits. The last chapter gives a suggestion for an ecological compatibility test (ECT) of thermal power plants. In modular form the ECT deals with the emission fields, waste heat, pollution burden of air and water, noise, loss of area and aesthetical aspects. Limits depending on local conditions and use of area will be discussed. (orig.)

  8. Geodesy problems in nuclear power plant construction

    International Nuclear Information System (INIS)

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

  9. Nuclear power plant piping prefabrication and assembly

    International Nuclear Information System (INIS)

    The piping design for nuclear power plants projects reveals, at the beginning, a modification through the application of new fabrication techniques for prefabrication and assembly. This report presents a fabrication methodology which aims to minimize the fabrication and assembly costs as well as to improve and assure quality. (Author)

  10. PWR reactors for BBR nuclear power plants

    International Nuclear Information System (INIS)

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

  11. Thermal and nuclear power plant design

    International Nuclear Information System (INIS)

    Research on heat transfer processes makes use of the concept of exergy or usable energy. The design of thermal power plants, which produce energy, make use of this fundamental entity, that conditions the final balance of work production. The different types of thermal power plant of the steam and gas type, together with nuclear power plants are reviewed. Heat losses, equal to more than half of the heat input, are the consequence of irreversible transformations of the energy of the fuel employed. It is important to implement resuperheating, so as to reduce the energy loss at high temperature. This is also enhanced by the use of a high steam pressure. The major parameters inherent in the design of the firebox associated with the gas turbine, are identified. The use of combined gas/steam cycles, allowing low exergy losses, has been spreading in recent years. The different systems used for nuclear power plants, for which the heat transfer aspect is crucial are examined. Future developments will depend on the high temperature behaviour of materials, because of the vital importance of thermal fatigue

  12. Programmed system for nuclear power plant protection

    International Nuclear Information System (INIS)

    The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described

  13. Decontamination techniques for BWR power generation plant

    International Nuclear Information System (INIS)

    The present report describes various techniques used for decontamination in BWR power generation plants. Objectives and requirements for decontamination in BWR power plants are first discussed focusing on reduction in dose, prevention of spread of contamination, cleaning of work environments, exposure of equipment parts for inspection, re-use of decontaminated resources, and standards for decontamination. Then, the report outlines major physical, chemical and electrochemical decontamination techniques generally used in BWR power generation plants. The physical techniques include suction of deposits in tanks, jet cleaning, particle blast cleaning, ultrasonic cleaning, coating with special paints, and flushing cleaning. The chemical decontamination techniques include the use of organic acids etc. for dissolution of oxidized surface layers and treatment of secondary wastes such as liquids released from primary decontamination processes. Other techniques are used for removal of penetrated contaminants, and soft and hard cladding in and on equipment and piping that are in direct contact with radioactive materials used in nuclear power generation plants. (N.K.)

  14. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    The Safety Guide gives design and some operational guidance for protection from fire and fire-related explosions in nuclear power plants (NPP). It confines itself to fire protection of items important to safety, leaving the aspects of fire protection not related to safety in NPP to be decided upon the basis of the national practices and regulations

  15. Hydroelectric power plant Irape - viability studies

    International Nuclear Information System (INIS)

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

  16. Nuclear power plants and the environment

    International Nuclear Information System (INIS)

    These proceedings reproduce the papers presented at the 6th Colloquium of the French Environment Law Society and a summary of the ensuing discussions. The topics covered include a comparative analysis of nuclear and environment law, pollution law and nuclear waste, as well as presentations on the setting up and operation of nuclear power plants, nuclear safety, liability and insurance. (NEA)

  17. Radiation protection in nuclear power plants

    International Nuclear Information System (INIS)

    The organization of workers' protection in a nuclear power plant is stated. Considering the nature and magnitude of potential risks and protection procedures, an inventory of occupational safety is made, taking account of accident statistics. It shows the credit to nuclear energy can be granted as to occupational safety

  18. Safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    A study about the safety analysis of nuclear power plant, giving emphasis to how and why to do is presented. The utilization of the safety analysis aiming to perform the licensing requirements is discussed, and an example of the Angra 2 and 3 safety analysis is shown. Some presented tendency of the safety analysis are presented and examples are shown.(E.G.)

  19. Nuclear power plant risk management overview

    International Nuclear Information System (INIS)

    In this paper, the author discusses the following topics: Requirements for nuclear power plant risk management; Cost benefits of risk management; Contributors to risk; Contributors to core damage for four phases of risk management; Examples of risk management recommendations derived from a risk model; Safety improvements identified; Risk lessons learned; and Methodology lessons learned

  20. Process control in nuclear power plants

    International Nuclear Information System (INIS)

    Optimum technical design of a nuclear power plant needs to be parallelled by effective process control in the stage of output operation. The author briefly demonstrates the pertinent criteria like operational organization, functional areas, crews, training of staff, process monitoring, industrial safety, incident prevention, and emergency manual. (DG)