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.)
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.)
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.)
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.)
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.)
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)
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
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
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.)
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.)
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)
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.)
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.
Hogerton, John F
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.
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)
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
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
Nosach, V.G.; Rogovoi, V.T.
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.
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
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
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
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.)
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…
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.)
A. L. Starzhinskij
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.
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
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.)
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
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.
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
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
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
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
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.)
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.)
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.)
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)
... 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),......
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.)
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
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
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
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
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
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
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.)
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.)
... 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'')...
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
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
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
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...
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
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
.... 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...
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.
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.
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)
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
Kumar, N.; Besuner, P.; Lefton, S.; Agan, D.; Hilleman, D.
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.
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
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
Small hydroelectric power plants are power plants of 1 - 10 MW. For a supplier, this is an unnatural limit. A more natural limit involves compact engine design and simplified control system. The article discusses most of the engine and electrotechnical aspects in the development, construction and operation of such a plant
The solar thermal power plant technology, the opportunities it presents and the developments in the market are outlined. The focus is on the technology of parabolic trough power plants, a proven technology for solar power generation on a large scale. In a parabolic trough power plant, trough-shaped mirrors concentrate the solar irradiation onto a pipe in the focal line of the collector. The thermal energy thus generated is used for electricity generation in a steam turbine. Parabolic trough plants can be combined with thermal storage and fossil or biomass fired heat exchangers to generate electricity even when the sun is not shining. Solar Millennium AG in Erlangen has developed the first power plant of this kind in Europe. After two years of construction the plant started operation in Southern Spain in 2008. This one and its sister projects are important steps leading the way for the whole market. The paper also covers the technological challenges, the key components used and the research and development activities concerning this technology. Solar thermal power plants are ideal for covering peak and medium loads in power grids. In hybrid operation they can also cover base-load. The Solar Chimney power plant, another striking technology for the conversion of solar into electric energy, is described briefly. The paper concludes with a look at the future - the import of solar energy from the deserts of North Africa to central Europe. (author)
17 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)
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
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.)
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.)
Yang, Guosheng; Tazoe, Hirofumi; Yamada, Masatoshi
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.
Yang, Guosheng; Tazoe, Hirofumi; Yamada, Masatoshi
(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
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
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
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.
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
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
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
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)
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)
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 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
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
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.
Randall, George A.
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)
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.)
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.)
Moreira, António H. J.; Freitas, Ricardo; Esteves, João Sena
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.
Moreira, António, 1957-; Freitas, Ricardo; Sepúlveda, João; Esteves, João Sena
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.
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.)
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.)
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)
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
Anand, Ashok Kumar; Nagarjuna Reddy, Thirumala Reddy
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.
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
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.)
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 %
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)
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
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.
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
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)
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
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)
Abdou, M.; Baker, C.; Brooks, J.; Ehst, D.; Mattas, R.; Smith, D.L.; DeFreece, D.; Morgan, G.D.; Trachsel, C.
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.
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)
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.)
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
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)
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
Bemš, J.; Knápek, J.; Králík, T.; Hejhal, M.; Kubančák, Ján; Vašíček, J.
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
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
Dharmateja Bandlamudi, Sahithi Avirneni
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.
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)
Purvis, James W.
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.
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
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)
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)
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
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.
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.
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.)
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.)
''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
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
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
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
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)
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
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)
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.)
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)
Paulusse, D C; Michaud, A; Paulusse, David C; Rowell, Nelson L; Michaud, Alain
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.
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)
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
Khabrana, Ahmed; Ageeli, Jaber
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...
Alduhov Oleg Aleksandrovich
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.
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
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)
''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.
"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.
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...
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
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)
Brugman, John; Hattar, Mai; Nichols, Kenneth; Esaki, Yuri
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
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)
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
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
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)
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
Hudson, C.R.; White, V.S.
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.
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.
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)
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
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.)
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)
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.)
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)
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.)
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)
Frimpter, Bonnie J.; And Others
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)
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
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
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...
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)
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
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)
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
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.
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)
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
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)
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
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...
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
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.)
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
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.)
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...
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
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
Jansson, S.A.; Anderson, L. [ABB Carbon AB, Finspong (Sweden)
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.
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
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.)
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)
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.
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...
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.)
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)
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
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.)
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
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
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
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.
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)
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)
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
Price, H. W.; Kistner, R.
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.
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
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)
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
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.)
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)
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...
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.)
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)
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.)
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.)
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.
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)
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
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
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
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)
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.)
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)
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
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
WU Peng; WEI Shuangying
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.
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)
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
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
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
Altin, Müfit; Teodorescu, Remus; Bak-Jensen, Birgitte; RODRIGUEZ, Pedro; Iov, Florin; Kjær, Philip C.
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...
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)
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
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)
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.)
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
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
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)
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
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.)
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)
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
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
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
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)
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)
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.)
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
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)
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
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
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.)
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)
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
Oh, Jeong Hoon; Lee, Hee Won; Song, Ki Chan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
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
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.
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
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
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.
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
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...